WorldWideScience

Sample records for nuclear development ceaden

  1. JPRS Report, Nuclear Developments.

    Science.gov (United States)

    2007-11-02

    COMERCIO 21 Aug] 23 NEAR EAST & SOUTH ASIA EGYPT Agreements Signed to Develop Domestic Uranium [AL-JUMHURIYAH 2 Aug] 24 INDIA Two Large...Empresas Nucleares Brasileiras S.A. (Nuclebras) to Industrias Nucleares do Brasil S.A. (INB), and trans- ferred the shares of its capital stock...96.622 authorizes the establishment of Uranium of Brasil S.A. as a subsidiary of INB, with headquarters in the city of Caldas, Minas Gerais State

  2. Nuclear Manpower Development

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, I. A.; Lee, K. B.; Shin, B. C. [KAERI, Daejeon (Korea, Republic of)

    2010-12-15

    The industry-university-research collaborative education is aiming at developing national nuclear human resources to satisfy with the increasing needs from the industry. For this efforts are being made to develop curricula customized to respective industry needs by improving existing ones. As the demand for training programs for the university students and domestic nuclear personnel was increasing owing to revitalization of nuclear industry, Nuclear Training Center (NTC) improved previous education programs to meet the needs. NTC has operated 2 education programs on research reactor experiments for the university students, and 18 programs on nuclear technology related experiment courses in 2010. Furthermore, the NTC developed new education programs related to 'standardized research reactor system design'. Also the request from universities for internship programs was increased by about three times in 2010 compared to those of the previous year, and this required to develop relevant curricula. In 2005, NTC developed KAERI-ACE, as a unique competency-based staff education system of Korea Atomic Energy Research Institute (KAERI). Based on the system, the NTC has performed 'systematic education'. In 2008, NTC was awarded Best HRD(Human Resource Development) in Public sector for the first time as a government-supported research institute. In 2009, the system was improved to become KAERI-ACE 2.0, based on which, in 2010, NTC improved and diversified education programs including various cyber training programs

  3. JPRS Report, Nuclear Developments

    Science.gov (United States)

    2016-03-24

    I Foreign Ministry on Algerian Nuclear Reactor [ZHONGGUO XINWEN SHE] .............................. I...Nuclear Facilities Urged [Seoul YONHAP] .................................................... 5 WPK’s ’Anti- War , Anti-Nuke’ Policy Viewed [KCNA...34 JPRS-TND-91-008 31 May 1991 CHINA 1 Algerian Nuclear Reactor Algeria signed a protocol on nuclear cooperation, in which China agreed

  4. Towards sustainable nuclear power development

    Energy Technology Data Exchange (ETDEWEB)

    Andrianov, Andrei A.; Murogov, Victor M.; Kuptsov, Ilya S. [Obninsk Institute for Nuclear Power Engineering of NNRU MEPhl, Obninsk, Kaluga Region (Russian Federation)

    2014-05-15

    The review of the current situation in the nuclear energy sector carried out in this article brings to light key problems and contradictions, development trends and prospects, which finally determine the role and significance of nuclear power as a factor ensuring a sustainable energy development. Authors perspectives on the most appropriate developments of nuclear power, which should be based on a balanced use of proven innovative nuclear technologies and comprehensive multilateral approaches to the nuclear fuel cycle are expressed. The problems of wording appropriate and essential requirements for new countries with respect to their preparedness to develop nuclear programs, taking into account their development level of industry and infrastructure as well as national heritages and peculiarities, are explained. It is also indicated that one of the major components of sustainability in the development of nuclear power, which legitimates its public image as a power technology, is the necessity of developing and promoting the concepts of nuclear culture, nuclear education, and professional nuclear ethics. (orig.)

  5. JPRS Report, Nuclear Developments

    Science.gov (United States)

    2016-03-24

    Pilotless Plane in 1991 [DAVAR 5 Nov] ....................................................... 19 Arens Rules Out Iraqi Nuclear Capability [Jerusalem...islands near is allowed to dispose of nuclear waste on the island, Prachuab Kiri Khan to see if there is any appropriate destroying not only the ecology ...controversial aspects of the issue has to Government was investing much more in the parallel do with a series of charges made by the ecological group

  6. JPRS Report, Nuclear Developments

    Science.gov (United States)

    2016-03-24

    50 SWEDEN Poll Surveys Views on Nuclear Power [DAGENS NYHETER 8 Mar] ........................................... 51 JPRS-TND...Indonesian Chong Chun-ki, chairman of the Korean Committee for 0600 GMT 9 Apr 91 Cultural Relations with Foreign Countries, indicated [Text] Indonesia has...taken additional mea- plants. In Sweden , where the nuclear power industry has sures. The leak occurred because of a neuparine plastic been most

  7. Nuclear Power Development in China

    Institute of Scientific and Technical Information of China (English)

    Lin Chengge; Li Shulan

    2009-01-01

    @@ China's nuclear power industry experienced such three stages as initiation, moderate development and active development. So far, there have been 11 nuclear power units in service in the Chinese mainland with a total installed capacity of 9 100 MW. In addition, there are 24 units being constructed or to be constructed as listed in the 11th Five-Year Plan.

  8. JPRS Report Nuclear Developments

    Science.gov (United States)

    2007-11-02

    Text] Furnas Chairman Camilo Pena has said the operation of the Angra I nuclear plant has been delayed once again. Furnas is suing the American...Westinghouse company and is demanding compensation for damages caused by a malfunction in the Angra I power generator. According to Camilo Pena, Angra I

  9. JPRS Report, Nuclear Developments

    Science.gov (United States)

    1989-06-14

    Decommissioning Prescription hour price for actual decommissioning. The state- financed KfK then took over the now worth- The Association of German Electricity...brothel receipts and gift lists. A slipup on the path to be melted down-with financing from the EC coffers in toward a brilliant future. Brussels within...area. Today, it is theincreasingly larger mountains of radioactive waste. Disneyland of nuclear technology. That is where the industrious Teko stands

  10. JPRS Report, Nuclear Developments

    Science.gov (United States)

    2016-03-24

    company (CNEA) responsible for the paralyzation of the activities supplies equipment to countries of Euratom (European at the Los Gigantes mine. stating...which were established with the active newspaper and its "funding" rather than the book. financial and technical support of China. Mr Malik, 52, who was...3 U.S., South Urge Nuclear Inspections of North /T7LE KOREA ttERALD 13.lw,, ............................. 4 U.S. Newspaper Story

  11. JPRS Report Nuclear Developments

    Science.gov (United States)

    2016-03-24

    The state of Mutually Assured tionals and produced by oppressed Black labour . South Destruction (M A D) in which the two superpowers are Africa is a...privatization of nuclear plants; criticized some aspects of the management of her predecessors, Admiral "To fulfill these objectives we need resources and per...not the cycle is rather complex to manage . The Brazilian know how long the commission will maintain its present effort is oriented in this direction

  12. Nuclear Power Development in China

    Institute of Scientific and Technical Information of China (English)

    2009-01-01

    China's nuclear power industry experienced such three stages as initiation,moderate development and active development.So far,there have been 11 nuclear power units in service in the Chinese mainland with a total installed capacity of 9 100 MW.In addition,there are 24 units being constructed or to be constructed as listed in the 11th Five-Year Plan.

  13. Nuclear Thermal Propulsion Development Risks

    Science.gov (United States)

    Kim, Tony

    2015-01-01

    There are clear advantages of development of a Nuclear Thermal Propulsion (NTP) for a crewed mission to Mars. NTP for in-space propulsion enables more ambitious space missions by providing high thrust at high specific impulse ((is) approximately 900 sec) that is 2 times the best theoretical performance possible for chemical rockets. Missions can be optimized for maximum payload capability to take more payload with reduced total mass to orbit; saving cost on reduction of the number of launch vehicles needed. Or missions can be optimized to minimize trip time significantly to reduce the deep space radiation exposure to the crew. NTR propulsion technology is a game changer for space exploration to Mars and beyond. However, 'NUCLEAR' is a word that is feared and vilified by some groups and the hostility towards development of any nuclear systems can meet great opposition by the public as well as from national leaders and people in authority. The public often associates the 'nuclear' word with weapons of mass destruction. The development NTP is at risk due to unwarranted public fears and clear honest communication of nuclear safety will be critical to the success of the development of the NTP technology. Reducing cost to NTP development is critical to its acceptance and funding. In the past, highly inflated cost estimates of a full-scale development nuclear engine due to Category I nuclear security requirements and costly regulatory requirements have put the NTP technology as a low priority. Innovative approaches utilizing low enriched uranium (LEU). Even though NTP can be a small source of radiation to the crew, NTP can facilitate significant reduction of crew exposure to solar and cosmic radiation by reducing trip times by 3-4 months. Current Human Mars Mission (HMM) trajectories with conventional propulsion systems and fuel-efficient transfer orbits exceed astronaut radiation exposure limits. Utilizing extra propellant from one additional SLS launch and available

  14. JPRS Report, Nuclear Developments

    Science.gov (United States)

    1989-07-14

    34out-of-round parts" was men- tritium treatment system headed for Pakistan by ship tioned. The cosmetic linguistic change took place prior and a few...34 waterproof ’-a Havanna deluxe, so to speak. At any rate, the regime in The most interesting new development in the compli- South Africa paid 45

  15. JPRS Report, Nuclear Developments

    Science.gov (United States)

    1989-04-25

    hafnium . Thanks to its technical ability, this multipurpose plant Condor II Development With Egypt To Continue will allow laboratory scale studies by...is a promise ingredients: antioxident 2246 and powdered aluminium , without institutions: It’s a promise without laws, and its MAPO, a rocket

  16. JPRS Report, Nuclear Developments

    Science.gov (United States)

    2016-03-24

    tists at the test base have succeeded in developing an crops and plants on 14 million hectares of land by electronic ( impulse ) static electric...fanned by their illegal behavior violating interna- not concealing their annoyance over this behavior . tional law. Thus, it was only natural that...the said. fuel for the reactor. India has been given the option of buying the engine However, Dr Srinivasan told a questioner that there was outright

  17. Nuclear target development

    Energy Technology Data Exchange (ETDEWEB)

    Greene, J.P.; Thomas, G.E.

    1995-08-01

    The Physics Division operates a target development laboratory that produces thin foil targets needed for experiments performed at the ATLAS and Dynamitron accelerators. Targets are not only produced for the Physics Division but also for other divisions and occasionally for other laboratories and universities. In the past year, numerous targets were fabricated by vacuum evaporation either as self-supporting foils or on various substrates. Targets produced included Ag, Au, {sup 10,11}B, {sup 138}Ba, Be, {sup 12}C, {sup 40}Ca, {sup 116}Cd, {sup 155,160}Gd, {sup 76}Ge, In, LID, {sup 6}LiH, Melamine, Mg, {sup 142,150}Nd, {sup 58}Ni, {sup 206,208}Pb, {sup 194}Pt, {sup 28}Si, {sup 144,148}Sm, {sup 120,122,124}Sn, Ta, {sup 130}Te, ThF{sub 4}, {sup 46,50}Ti, TiH, U, UF{sub 4}, {sup 182}W and {sup 170}Yb. Polypropylene and aluminized polypropylene, along with metallized Mylar were produced for experiments at ATLAS. A number of targets of {sup 11}B of various thickness were made for the DEP 2-MeV Van de Graff accelerator. An increased output of foils fabricated using our small rolling mill included targets of Au, C, {sup 50}Cr, Cu, {sup 155,160}Gd, Mg, {sup 58}Ni, {sup 208}Pb, {sup 105,110}Pd. Sc, Ti, and {sup 64,66}Zn.

  18. Development of Nuclear Analytical Technology

    Energy Technology Data Exchange (ETDEWEB)

    Park, Yong Joon; Kim, J. Y.; Sohn, S. C. (and others)

    2007-06-15

    The pre-treatment and handling techniques for the micro-particles in swipe samples were developed for the safeguards purpose. The development of screening technique for the swipe samples has been established using the nuclear fission track method as well as the alpha track method. The laser ablation system to take a nuclear particle present in swipe was designed and constructed for the determination of the enrichment factors for uranium or plutonium, and its performance was tested in atmosphere as well as in vacuum. The optimum conditions for the synthesis of silica based micro-particles were obtained for mass production. The optimum ion exchange resin was selected and the optimum conditions for the uranium adsorption in resin bead technique were established for the development of the enrichment factor for nuclear particles in swipe. The established technique was applied to the swipe taken directly from the nuclear facility and also to the archive samples of IAEA's environmental swipes. The evaluation of dose rate of neutron and secondary gamma-ray for the radiation shields were carried out to design the NIPS system, as well as the evaluation of the thermal neutron concentration effect by the various reflectors. D-D neutron generator was introduced as a neutron source for the NIPS system to have more advantages such as easier control and moderation capability than the {sup 252}Cf source. Simulated samples for explosive and chemical warfare were prepared to construct a prompt gamma-ray database. Based on the constructed database, a computer program for the detection of illicit chemical and nuclear materials was developed using the MATLAB software.

  19. History of nuclear technology development in Japan

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-04-29

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

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

    Science.gov (United States)

    Hull, Daniel M.

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

  1. Nuclear Security, Disarmament and Development

    Science.gov (United States)

    Salam, Abdus

    The world's stock of nuclear weapons, which was three in 1945, has been growing ever since and is 50,OOOa in 1985. Nearly two trillion dollars of the public funds have been spent over the years to improve their destructive power, and the means of delivering them. One indicator of the awful power of these weapons is that the explosive yield of the nuclear weapons stockpiled today by the US, USSR, UK, France, and China is equivalent to one million Hiroshima bombs. Less than 1,000 of these 50,000 weapons could destroy USA and USSR. A thousand more in an all-out nuclear exchange could destroy the world as a habitable planet, ending life for the living and the prospects of life for those not yet born, sparing no nation, no region of the world…

  2. MSFC Nuclear Propulsion Materials Development

    Science.gov (United States)

    Rogers, J. R.; Cook, B.

    2004-01-01

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

  3. Nuclear Actin in Development and Transcriptional Reprogramming.

    Science.gov (United States)

    Misu, Shinji; Takebayashi, Marina; Miyamoto, Kei

    2017-01-01

    Actin is a highly abundant protein in eukaryotic cells and dynamically changes its polymerized states with the help of actin-binding proteins. Its critical function as a constituent of cytoskeleton has been well-documented. Growing evidence demonstrates that actin is also present in nuclei, referred to as nuclear actin, and is involved in a number of nuclear processes, including transcriptional regulation and chromatin remodeling. The contribution of nuclear actin to transcriptional regulation can be explained by its direct interaction with transcription machineries and chromatin remodeling factors and by controlling the activities of transcription factors. In both cases, polymerized states of nuclear actin affect the transcriptional outcome. Nuclear actin also plays an important role in activating strongly silenced genes in somatic cells for transcriptional reprogramming. When these nuclear functions of actin are considered, it is plausible to speculate that nuclear actin is also implicated in embryonic development, in which numerous genes need to be activated in a well-coordinated manner. In this review, we especially focus on nuclear actin's roles in transcriptional activation, reprogramming and development, including stem cell differentiation and we discuss how nuclear actin can be an important player in development and cell differentiation.

  4. Nuclear Technology for the Sustainable Development Goals

    Science.gov (United States)

    Darby, Iain

    2017-01-01

    Science, technology and innovation will play a crucial role in helping countries achieve the ambitious Sustainable Development Goals (SDGs). Since the discovery of nuclear fission in the 1930s, the peaceful applications of nuclear technology have helped many countries improve crops, fight pests, advance health, protect the environment and guarantee a stable supply of energy. Highlighting the goals related to health, hunger, energy and the environment, in this presentation I will discuss how nuclear technology contributes to the SDGs and how nuclear technology can further contribute to the well-being of people, help protect the planet and boost prosperity.

  5. Nuclear Cryogenic Propulsion Stage Affordable Development Strategy

    Science.gov (United States)

    Doughty, Glen E.; Gerrish, H. P.; Kenny, R. J.

    2014-01-01

    The development of nuclear power for space use in nuclear thermal propulsion (NTP) systems will involve significant expenditures of funds and require major technology development efforts. The development effort must be economically viable yet sufficient to validate the systems designed. Efforts are underway within the National Aeronautics and Space Administration's (NASA) Nuclear Cryogenic Propulsion Stage Project (NCPS) to study what a viable program would entail. The study will produce an integrated schedule, cost estimate and technology development plan. This will include the evaluation of various options for test facilities, types of testing and use of the engine, components, and technology developed. A "Human Rating" approach will also be developed and factored into the schedule, budget and technology development approach.

  6. Nuclear Concrete Materials Database Phase I Development

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-05-01

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

  7. Trends in nuclear medicine in developing countries.

    Science.gov (United States)

    Dondi, Maurizio; Kashyap, Ravi; Paez, Diana; Pascual, Thomas; Zaknun, John; Bastos, Fernando Mut; Pynda, Yaroslav

    2011-12-01

    This article describes trends in nuclear medicine in the developing world as noted by nuclear medicine professionals at the International Atomic Energy Agency (IAEA). The trends identified are based on data gathered from several sources, including information gathered through a database maintained by the IAEA; evaluation of country program frameworks of various IAEA Member States; personal interactions with representatives in the nuclear medicine field from different regions of the world; official proceedings and meeting reports of the IAEA; participation in numerous national, regional, and international conferences; discussions with the leadership of major professional societies; and relevant literature. The information presented in this article relied on both objective and subjective observations. The aims of this article were to reflect on recent developments in the specialty of nuclear medicine and to envision the directions in which it is progressing. These issues are examined in terms of dimensions of practice, growth, and educational and training needs in the field of nuclear medicine. This article will enable readers to gain perspective on the status of nuclear medicine practice, with a specific focus on the developing world, and to examine needs and trends arising from the observations.

  8. Development of nuclear transmutation technology

    Energy Technology Data Exchange (ETDEWEB)

    Park, Won Seok; Song, Tae Young; Yoo, Jae Kwon; Choi, Byung Ho; Shin, Hee Sung; Gil, Chung Sup; Kim, Jung Do

    1997-08-01

    A basic characteristics and neutronic code development for accelerator driven subcritical reactor have been performed. In the field of basic characteristic study, the world-wide technical trends for a subcritical reactor has been investigated and some new directions for the subcritical system development were investigated. For the analysis of subcritical reactor core, a Montecarlo depletion code was developed by combining LAHET code with ORIGEN2 code. In addition, one-point kinetics equation for subcritical reactor programmed in order to analyze the dynamic behavior of subcritical core. (author). 26 tabs., 49 figs.

  9. Historical aspects of the nuclear right development; Aspectos historicos en el desenvolviminento del derecho nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Puig, Diva E. [Universidad de la Republica, Montevideo (Uruguay). Facultad de Derecho

    1999-04-01

    This paper analyses the historical aspects of the nuclear right development. It makes the evolution of the fundamental principles of nuclear right, in special, the civil responsibility for nuclear damages. (author)

  10. Radiation chemistry for modern nuclear energy development

    Science.gov (United States)

    Chmielewski, Andrzej G.; Szołucha, Monika M.

    2016-07-01

    Radiation chemistry plays a significant role in modern nuclear energy development. Pioneering research in nuclear science, for example the development of generation IV nuclear reactors, cannot be pursued without chemical solutions. Present issues related to light water reactors concern radiolysis of water in the primary circuit; long-term storage of spent nuclear fuel; radiation effects on cables and wire insulation, and on ion exchangers used for water purification; as well as the procedures of radioactive waste reprocessing and storage. Radiation effects on materials and enhanced corrosion are crucial in current (II/III/III+) and future (IV) generation reactors, and in waste management, deep geological disposal and spent fuel reprocessing. The new generation of reactors (III+ and IV) impose new challenges for radiation chemists due to their new conditions of operation and the usage of new types of coolant. In the case of the supercritical water-cooled reactor (SCWR), water chemistry control may be the key factor in preventing corrosion of reactor structural materials. This paper mainly focuses on radiation effects on long-term performance and safety in the development of nuclear power plants.

  11. Robot development for nuclear material processing

    Energy Technology Data Exchange (ETDEWEB)

    Pedrotti, L.R.; Armantrout, G.A.; Allen, D.C.; Sievers, R.H. Sr.

    1991-07-01

    The Department of Energy is seeking to modernize its special nuclear material (SNM) production facilities and concurrently reduce radiation exposures and process and incidental radioactive waste generated. As part of this program, Lawrence Livermore National Laboratory (LLNL) lead team is developing and adapting generic and specific applications of commercial robotic technologies to SNM pyrochemical processing and other operations. A working gantry robot within a sealed processing glove box and a telerobot control test bed are manifestations of this effort. This paper describes the development challenges and progress in adapting processing, robotic, and nuclear safety technologies to the application. 3 figs.

  12. Nuclear Power: Entering the Stage of Active Development

    Institute of Scientific and Technical Information of China (English)

    Xu Lianyi; Zhu Li

    2009-01-01

    @@ Development course Since 1970 when the construction preparation of Qinshan No. 1 Nuclear Power Plant started, China's nuclear power industry has grown out of nothing, and then adjusted the step from moderate development to vigorous development. In this course, China's nuclear power equipment manufacturing industry has also been unceasingly developing and strengthening itself with the construction of nuclear power plants one by one.

  13. Nuclear energy and sustainable development; Energia Nuclear y desarrollo sostenible

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez, E.

    2005-07-01

    To sustain decent environmental conditions, it is essential to contain the emission of greenhouse gases. to a great extent, this can be achieved by reducing the almost exclusive dependence of fossil fuels for producing electricity and by championing nuclear energy and the renewable, which in the end are the least contaminating. Specifically, operation of the European nuclear fleet avoids the yearly emission of 700 million tons of CO{sub 2} to the atmosphere. The need to combat climate change is very serious and increasingly imminent, especially if we remember that the World Health Organization has said that climate change could eventually cause 300,000 deaths. The different social players are aware of the problem. In fact, the European Union's Cabinet of Ministers approved the post-kyoto Environmental Strategy, which underlines the need to reduce CO{sub 2} emissions by 80% by the year 2050. It seems obvious that, in the long run, technological research and development will be fundamental pieces in the battle against environmental change and in the effort to one day provide 2,000 million people with access to electricity. (Author)

  14. Development of Nuclear Materials and Degradation Database

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-10-15

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

  15. The Development of French Nuclear Forces

    Science.gov (United States)

    1987-11-01

    developments under the Fifth Republic, first, during the presidency of de Gaulle and then of his successors, Pompidou , Giscard, and Mitterrand. The era of the...program was the establishment of an atomic research center at Chatillon, near Paris, with the dual purpose of providing training in nuclear physics and...decision did, essentially, was to provide official government sanction for a policy already in place. Policy This policy centered on the development

  16. Nuclear fuels: Development, processing and disposal

    Energy Technology Data Exchange (ETDEWEB)

    Allday, C.

    1982-08-01

    The successful development of the world's energy resources has enabled industries in the more advanced countries to provide the economic basis on which improved living standards are based. As the less well-developed countries seek to improve their standards of living the pressure on existing energy resources will increase. In this context it is essential not to allow the current industrial recession in the developed countries, with its associated apparent abundancy of coal, oil and gas, to mask the longer-term energy situation. It is not here proposed to discuss the role of nuclear power in the energy scene except to say that, with the continuing need to develop energy resources, nuclear as a proven safe and economic system - will have a vital role to fulfil in meeting the world's future energy demands. This paper is concerned with the development of nuclear fuel and the industry which has grown around it during the last 30 years. It shall concentrate on its development in this country and describe the history and activities of BNFL.

  17. Nuclear Thermal Rocket (NTR) Development Risk Communication

    Science.gov (United States)

    Kim, Tony

    2014-01-01

    There are clear advantages of development of a Nuclear Thermal Rocket (NTR) for a crewed mission to Mars. NTR for in-space propulsion enables more ambitious space missions by providing high thrust at high specific impulse (approximately 900 sec) that is 2 times the best theoretical performance possible for chemical rockets. Missions can be optimized for maximum payload capability to take more payload with reduced total mass to orbit; saving cost on reduction of the number of launch vehicles needed. Or missions can be optimized to minimize trip time significantly to reduce the deep space radiation exposure to the crew. NTR propulsion technology is a game changer for space exploration. However, "NUCLEAR" is a word that is feared and vilified by some groups and the hostility towards development of any nuclear systems can meet great opposition by the public as well as from national leaders and people in authority. Communication of nuclear safety will be critical to the success of the development of the NTR. Why is there a fear of nuclear? A bomb that can level a city is a scary weapon. The first and only times the Nuclear Bomb was used in a war was on Hiroshima and Nagasaki during World War 2. The "Little Boy" atomic bomb was dropped on Hiroshima on August 6, 1945 and the "Fat Man" on Nagasaki 3 days later on August 9th. Within the first 4 months of bombings, 90- 166 thousand people died in Hiroshima and 60-80 thousand died in Nagasaki. It is important to note for comparison that over 500 thousand people died and 5 million made homeless due to strategic bombing (approximately 150 thousand tons) of Japanese cities and war assets with conventional non-nuclear weapons between 1942- 1945. A major bombing campaign of "firebombing" of Tokyo called "Operation Meetinghouse" on March 9 and 10 consisting of 334 B-29's dropped approximately1,700 tons of bombs around 16 square mile area and over 100 thousand people have been estimated to have died. The declaration of death is very

  18. Development of Nanomaterials for Nuclear Energetics

    Science.gov (United States)

    Petrunin, V. F.

    Structure and properties peculiarities of the nanocrystalline powders give the opportunity to design new and to develop a modernization of nuclear energy industry materials. It was shown experimentally, that addition of 5-10% uranium dioxide nanocrystalline powder to traditional coarse powder allows to decrease the sintering temperature or to increase the fuel tablets size of grain. Similar perspectives for the technology of neutron absorbing tablets of control-rod modernization are shown by nanopowder of dysprosium hafnate changing instead now using boron carbide. It is powders in nanocrystalline state get an opportunity to sinter them and to receive compact tablet with 8,2-8,4 g/cm2 density for automatic defence system of nuclear reactor. Resource of dysprosium hafnate ceramics can be 18-20 years instead 4-5 years for boron carbide. To step up the radiation-damage stability of fuel element jacket material was suggested to strengthen a heat-resistant ferrite-martensite steel by Y2O3 nanocrystalline powder addition. Nanopowder with size of particles 560 nm and crystallite size 9 nm was prepeared by chemical coprecipitation method. To make lighter the container for transport and provisional disposal of exposed fuel from nuclear reactor a new boron-aluminium alloy called as boral was developed. This composite armed with nanopowders of boron-containing materials and heavy metals oxides can replace succesburnt-up corrosion-resistant steels.

  19. Development of nuclear equipment qualification technology

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Heon O; Kim, Wu Hyun; Kim, Jin Wuk; Kim, Jeong Hyun; Lee, Jeong Kyu; Kim, Yong Han; Jeong, Hang Keun [Korea Institute of Machinery and Materials, Taejon (Korea)

    1999-03-01

    In order to enhance testing and evaluation technologies, which is one of the main works of the Chanwon branch of KIMM(Korea Institute of Machinery and Materials), in addition to the present work scope of the testing and evaluation in the industrial facilities such as petroleum and chemical, plants, the qualification technologies of the equipments important to safety used in the key industrial facilities such as nuclear power plants should be localized: Equipments for testing and evaluation is to be set up and the related technologies must be developed. In the first year of this study, of vibration aging qualification technologies of equipments important to safety used in nuclear power plants have been performed. (author). 27 refs., 81 figs., 17 tabs.

  20. Proceedings of the nuclear Inter Jura`93. Nuclear energy and sustainable development: the role of law

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    The importance of the law for the future of the nuclear energy within the context of the sustainable development is discussed in this Nuclear Inter Jura - Rio`93, which contains the individual papers, reports of working groups and a proposal of standards of good behavior for the civilian nuclear industry. This congress is divided in five sections: licensing and decommissioning; nuclear liability cover; international nuclear trade; radiological protection and radioactive waste management.

  1. Nuclear Waste, Risks and Sustainable Development

    Energy Technology Data Exchange (ETDEWEB)

    Karlsson, Mikael [Swedish Society for Nature Conservation, Stockholm (Sweden); Swahn, Johan [Swedish NGO Office for Nuclear Waste Review (MKG), Goeteborg (Sweden)

    2006-09-15

    The proposed Swedish nuclear waste project is not in line with the three principles of sustainable development. In some aspects, it is not even compatible with Swedish law and ought therefore not to be given a permit under present circumstances. In our view, a number of measures need to be taken to improve the likelihood that the waste repository will promote and not further jeopardise sustainable development. One obvious measure would be to follow the recommendations concerning polluter pays principle put forward by the 2004 governmental committee. Further, it can be credible argued that the focus of the present disposal process has not been to find the best site and method from environmental point of view. If the precautionary principle is to be applied (and Swedish law is to be followed), alternative methods and sites have to be examined to see if they could provide better long-term safety. Concerning method, there are options that deserve much more attention such as so called 'deep boreholes'. In this approach the nuclear waste is placed in deep boreholes at depths of 2-4 km. Studies show that the long-term environmental safety and the possibility of hindering intentional intrusion may improve using the deep borehole method. Regarding localisation, one option would be to avoid siting the repository on the coast, but in what is called a 'recharge area'. In such an area groundwater on a regional scale travels downwards into the bedrock and it may take 50 000 years for a release of radioactivity to reach the surface, compared to less than 100 years with a coastal siting. Evidently, there may be better methods and sites than those now proposed by the Swedish nuclear industry. These options must be examined in detail before a decision is taken to implement the KBS method at a coastal site. If such methods or sites are found better they have to be used in the first place. Improvements are also necessary when it comes to public participation. We

  2. Current Developments in Nuclear Density Functional Methods

    CERN Document Server

    Dobaczewski, J

    2010-01-01

    Density functional theory (DFT) became a universal approach to compute ground-state and excited configurations of many-electron systems held together by an external one-body potential in condensed-matter, atomic, and molecular physics. At present, the DFT strategy is also intensely studied and applied in the area of nuclear structure. The nuclear DFT, a natural extension of the self-consistent mean-field theory, is a tool of choice for computations of ground-state properties and low-lying excitations of medium-mass and heavy nuclei. Over the past thirty-odd years, a lot of experience was accumulated in implementing, adjusting, and using the density-functional methods in nuclei. This research direction is still extremely actively pursued. In particular, current developments concentrate on (i) attempts to improve the performance and precision delivered by the nuclear density-functional methods, (ii) derivations of density functionals from first principles rooted in the low-energy chromodynamics and effective th...

  3. Nuclear Power:Entering the Stage of Active Development

    Institute of Scientific and Technical Information of China (English)

    2009-01-01

    Development course Since 1970 when the construction preparation of Qinshan No.1 Nuclear Power Plant started,China's nuclear power industry has grown out of nothing,and then adjusted the step from moderate development to vigorous development.In this course,China's nuclear power equipment manufacturing industry has also been unceasingly developing and strengthening itself with the construction of nuclear power plants one by one.

  4. Worldwide Report, Nuclear Development and Proliferation

    Science.gov (United States)

    1985-08-21

    cannot were from Canada - also cited submit a grab- bag of ill-conceived Nicaragua as "the model of a new proposals.’ kind of society" and "a symbol...Export Development b e the ripos edthat nuclear supplies and facilities Corp. or Insure the consortium’ by the Turki hat a negativer will not be used to...description of magnetite rejection, the uses of aluminum in medium-sized vessels, the handling of propellants, off-shore platforms, continuous biodigestion

  5. DCS emulator development for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Nakashima, Y. [Hitachi Canada Ltd., Power and Industry Div., Mississauga, Ontario (Canada); Ishii, K.; Chiba, D. [Hitachi Ltd., Information and Control Systems Div., Ibaraki-ken (Japan)

    2009-07-01

    Continual training of operators is one of the principal means by which Nuclear Power Plant (NPP) operational efficiency can be improved. Since this training cannot take place in the actual NPP, NPP simulator applications must be used instead. While digitalization scope of Instrumentation and Control (I and C) systems has been expanded to the entire plant by using Distributed Control System (DCS) implementation, Hitachi has implemented DCS emulator on a general purpose Personal Computer (PC) and applied it to simulator applications. This paper reviews such DCS emulator development for NPP by Hitachi. (author)

  6. Development on dynamic nuclear polarized targets

    CERN Document Server

    Penttila, S I

    2002-01-01

    Our interest in understanding the spin content of the nucleon has left its marks on the recent development of the dynamic nuclear polarized (DNP) targets. This can be seen from the targets developed at CERN and SLAC for the measurement of the polarized spin structure functions in deep inelastic scattering. The results of the experiments indicated that less than 30% of the nucleon spin is carried by the quarks. This unpredicted small value initiated planning of new polarized target experiments to determine the gluon polarization on the nucleon using polarized real photons and polarized /sup 6/LiD targets. In several facilities very intense polarized photon beams are available at a wide energy range. During the next few years these photon beams with DNP targets will be used to test the fundamental GDH sum rule. Other DNP target developments are also discussed. (61 refs).

  7. Development of nuclear energetics in Latvia

    Energy Technology Data Exchange (ETDEWEB)

    Mikelsons, Karlis; Ekmanis, Juris; Gavars, Valdis; Tomsons, Elmars; Zeltins, Namejs

    2010-09-15

    A scientific nuclear reactor was launched in 1961, and a critical test assembly - in 1965. A unique gamma-ray source was created, and it was proposed to form an industrial production plant of radiation chemistry at Ignalina NPP. In order to supply Latvia with electricity, a site was chosen in the 1980-ties for a base-power nuclear power plant. After the restoration of independence the scientists of Latvia continue taking part in international projects of nuclear fusion and the 4th generation nuclear reactors. The supply of Latvia with electricity in a more distant period will be possible by using nuclear energy.

  8. U.S. Strategic Nuclear Forces: Background, Developments, and Issues

    Science.gov (United States)

    2017-02-10

    Secretary of Defense Hagel ordered an internal review of nuclear weapons personnel issues and commissioned another outside study of morale and...U.S. Strategic Nuclear Forces: Background, Developments, and Issues Amy F. Woolf Specialist in Nuclear Weapons Policy February 10, 2017...

  9. Development of human resources for Indian nuclear power programme

    Indian Academy of Sciences (India)

    R B Grover; R R Puri

    2013-10-01

    The continuing research and development on nuclear technology by research establishments in the country and maturing of Indian industry have brought the nuclear energy programme in India to a stage where it is poised to take a quantum leap forward. The vision of expansion of nuclear power also requires a wellstructured specialized human resource development programme. This paper discusses the requirements of the human resource development programme for nuclear energy, the challenges in the way of its realization, its national and international status and traces the history of nuclear education in the country. It brings out the linkage of human resource development programme with the nuclear energy programme in the country. It also describes the initiatives by the university system in the area of nuclear education and support provided by the Department of Atomic Energy to the university system by way of extra-mural funding and by providing access to research facilities.

  10. Worldwide Report, Nuclear Development and Proliferation

    Science.gov (United States)

    1986-07-09

    Agreement (Martin F. Yriart; Buenos Aires AMBITO FINANCIERO , 12 May 86) 22 NEAR EAST/SOUTH ASIA BANGLADESH OBSERVER: Nuclear Technology Growth Playing...BRAZILIAN NUCLEAR AGREEMENT Buenos Aires AMBITO FINANCIERO in Spanish 12 May 86 p 13 [Article by Martin F. Yriart: "Historic Agreement Between Brazil and...and a mem- ber of the nuclear policy commission advising Brazil’s President Jose Sarney, told AMBITO FINANCIERO this yesterday. This announcement

  11. A study on future nuclear reactor technology and development strategy

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S. Y.; Kim, S. H.; Sohn, D. S.; Suk, S. D.; Zee, S. K.; Yang, M. H.; Kim, H. J.; Park, W. S

    2000-12-01

    Development of nuclear reactor and fuel cycle technology for future is essential to meet the current issues such as enhancement of nuclear power reactor safety, economically competitive with gas turbine power generation, less production of radioactive waste, proliferation resistant fuel cycle, and public acceptance in consideration of lack of energy resources in the nuclear countries worldwide as well as in Korea. This report deals with as follows, 1) Review the world energy demand and supply perspective and analyse nature of energy and sustainable development to set-up nuclear policy in Korea 2) Recaptitulate the current long term nuclear R and D activities 3) Review nuclear R and D activities and programs of USA, Japan, France, Russia, international organizations such as IAEA, OECD/NEA 4) Recommend development directions of nuclear reactors and fuels.

  12. Nuclear Energy Readiness Indicator Index (NERI): A benchmarking tool for assessing nuclear capacity in developing countries

    Energy Technology Data Exchange (ETDEWEB)

    Saum-Manning,L.

    2008-07-13

    Declining natural resources, rising oil prices, looming climate change and the introduction of nuclear energy partnerships, such as GNEP, have reinvigorated global interest in nuclear energy. The convergence of such issues has prompted countries to move ahead quickly to deal with the challenges that lie ahead. However, developing countries, in particular, often lack the domestic infrastructure and public support needed to implement a nuclear energy program in a safe, secure, and nonproliferation-conscious environment. How might countries become ready for nuclear energy? What is needed is a framework for assessing a country's readiness for nuclear energy. This paper suggests that a Nuclear Energy Readiness Indicator (NERI) Index might serve as a meaningful basis for assessing a country's status in terms of progress toward nuclear energy utilization under appropriate conditions. The NERI Index is a benchmarking tool that measures a country's level of 'readiness' for nonproliferation-conscious nuclear energy development. NERI first identifies 8 key indicators that have been recognized by the International Atomic Energy Agency as key nonproliferation and security milestones to achieve prior to establishing a nuclear energy program. It then measures a country's progress in each of these areas on a 1-5 point scale. In doing so NERI illuminates gaps or underdeveloped areas in a country's nuclear infrastructure with a view to enable stakeholders to prioritize the allocation of resources toward programs and policies supporting international nonproliferation goals through responsible nuclear energy development. On a preliminary basis, the indicators selected include: (1) demonstrated need; (2) expressed political support; (3) participation in nonproliferation and nuclear security treaties, international terrorism conventions, and export and border control arrangements; (4) national nuclear-related legal and regulatory mechanisms; (5

  13. Promotion of Bilateral Cooperative Programs in Nuclear Human Resources Development

    Energy Technology Data Exchange (ETDEWEB)

    Lee, E. J.; Han, K. W.; Nam, Y. M. (and others)

    2009-08-15

    The purpose of this project is strengthening of bilateral cooperation with those countries for sharing Korea's technology, and providing of education and training on Korean experience regarding national nuclear policy, technology self reliance, and technology itself, in the field of nuclear power generation and the application of radioisotopes and radiation. This project covers an analysis on the need of nuclear human resource development in countries having interest in the introduction of nuclear power and/or promotion of the use of nuclear energy, and provision of courses on 'nuclear power policy, planning and management' and 'design and operation of nuclear research reactor, and application of radiation technology' along with the country specific needs. Education and training of key members in nuclear energy development from Egypt: It was implemented through bilateral cooperation and support by KOICA program. The first part, which targeted staff members from Egypt Nuclear Commission, was held for 2 months providing a KOICA course on policy, planning and management for nuclear power project, and second part was on the job training in Korea Hydro and Nuclear Power and Korea Institute of Nuclear Safety, KAERI respectively. On the job training of 1 scientist from Vietnam was implemented on the basis of bilateral cooperation in a research laboratory on radioactive waste treatment technology, at KAERI. Education and training for scientists from South East RCA countries were carried out for 11 participants from Vietnam, Thailand, Indonesia, China, Pakistan, Malaysia, Philippines, and Bangladesh. The course dealt with nuclear research reactor and radiation application technology. Development of nuclear education and training programs for key persons involved in nuclear power projects from countries of Middle East: The developed program consists of 15 courses addressing 3 technical levels, i.e. high level policy makers, middle level project

  14. Argentina: Nuclear power development and Atucha 2

    Energy Technology Data Exchange (ETDEWEB)

    Nogarin, Mauro

    2015-08-15

    In 2014, nuclear energy generated about 5,257 GWh of electricity or a total share of 4.05 % of the total electrical energy of about 129,747.63 GWh kWh produced in Argentina and there has been a trend for this production to increase. Argentina currently has a nuclear production capacity of 1,010 megawatts of electrical energy. However, when the Atucha 2 nuclear power plant is completed and starts commercial operation, it will add 745 megawatts to this electrical production capacity. There are two sites with nuclear power plants in Argentina: Atucha and Embalse. The Embalse nuclear power plant went into operation in 1984. At the Atucha site, the Atucha-1 nuclear power plant started operation in 1974. It was the first nuclear power plant in Latin America. Construction of Atucha-2 started in 1981 but advanced slowly due to funding and was suspended in 1994 when the plant was 81 % built. In 2003, new plans were approved to complete the Atucha 2. I summer 2014 the plant went critical for the first time. The construction was completed under a contract with AECL.

  15. Strategic position and development prospects of nuclear energy in China

    Institute of Scientific and Technical Information of China (English)

    SHEN Wenquan

    2007-01-01

    By analyzing the challenges of China's energy supply, an excellent perspective of nuclear power development in the country has been described. Taking into account the near-, mid-, and long-term development requirements,a comprehensive, coordinated and sustainable nuclear power program is proposed. Thus, our national nuclear industry can not only catch up with the world's advanced level in proper time, but also possess enough stamina for sustainability.

  16. 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

  17. Current Development of Nuclear Thermal Propulsion technologies at the Center for Space Nuclear Research

    Energy Technology Data Exchange (ETDEWEB)

    Robert C. O' Brien; Steven K. Cook; Nathan D. Jerred; Steven D. Howe; Ronald Samborsky; Daniel Brasuell

    2012-09-01

    Nuclear power and propulsion has been considered for space applications since the 1950s. Between 1955 and 1972 the US built and tested over twenty nuclear reactors / rocket engines in the Rover/NERVA programs1. The Aerojet Corporation was the prime contractor for the NERVA program. Modern changes in environmental laws present challenges for the redevelopment of the nuclear rocket. Recent advances in fuel fabrication and testing options indicate that a nuclear rocket with a fuel composition that is significantly different from those of the NERVA project can be engineered; this may be needed to ensure public support and compliance with safety requirements. The Center for Space Nuclear Research (CSNR) is pursuing a number of technologies, modeling and testing processes to further the development of safe, practical and affordable nuclear thermal propulsion systems.

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

    Energy Technology Data Exchange (ETDEWEB)

    Robert C. O' Brien

    2001-09-01

    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.

  19. Nuclear forces from EFT: Recent developments

    Directory of Open Access Journals (Sweden)

    Meißner U.-G.

    2010-04-01

    Full Text Available Nuclear forces are considered based on chiral perturbation theory with and without explicit ∆-isobar degrees of freedom. We discuss the subleading corrections to chiral three-nucleon forces in the ∆-less formalism which contain no additional free parameters. In the formalism with explicit ∆-isobar we present the complete next-to-next-to-leading order analysis of isospin-conserving and next-to-leading order analysis of isospinviolating nuclear forces. The perturbative expansion of nuclear forces in the ∆-full case is shown to have much better convergence compared with the ∆-less theory where the ∆-resonance is integrated out and is encoded in certain low-energy constants.

  20. Nuclear energy consumption and economic growth in nine developed countries

    Energy Technology Data Exchange (ETDEWEB)

    Wolde-Rufael, Yemane [135 Carnwath Road, London SW6 3HR (United Kingdom); Menyah, Kojo [London Metropolitan Business School, London Metropolitan University, 84 Moorgate, London EC2M 6SQ (United Kingdom)

    2010-05-15

    This article attempts to test the causal relationship between nuclear energy consumption and real GDP for nine developed countries for the period 1971-2005 by including capital and labour as additional variables. Using a modified version of the Granger causality test developed by Toda and Yamamoto (1995), we found a unidirectional causality running from nuclear energy consumption to economic growth in Japan, Netherlands and Switzerland; the opposite uni-directional causality running from economic growth to nuclear energy consumption in Canada and Sweden; and a bi-directional causality running between economic growth and nuclear energy consumption in France, Spain, the United Kingdom and the United States. In Spain, the United Kingdom and the USA, increases in nuclear energy consumption caused increases in economic growth implying that conservation measures taken that reduce nuclear energy consumption may negatively affect economic growth. In France, Japan, Netherlands and Switzerland increases in nuclear energy consumption caused decreases in economic growth, suggesting that energy conservation measure taken that reduce nuclear energy consumption may help to mitigate the adverse effects of nuclear energy consumption on economic growth. In Canada and Sweden energy conservation measures affecting nuclear energy consumption may not harm economic growth. (author)

  1. The Development of Nuclear Propulsion in the Navy

    Science.gov (United States)

    1960-03-29

    nuclear power for ship propulsion . The man who approved this project on his own cognizance was Rear Admiral Harold G. Bowen, then Chief of the old...their basic objective, the development of nuclear power for ship propulsion . However, they faced a formidable obstacle. Because of severe security...officials on the possibility of the application of nuclear power to ship propulsion . General Groves stated that the chief handicap was the limited

  2. Worldwide Report, Nuclear Development and Proliferation

    Science.gov (United States)

    2007-11-02

    nuclear superiority. Speaking in the general debate in the Disarm- ament Commission, the Indian delegatet Miss Savitri Kunadi, on Wednesday saidthe...lines: "Experiments carried out so far on test auto- clave indicate that some more modifications of the plant may be required before commissioning

  3. Worldwide Report, Nuclear Development and Proliferation

    Science.gov (United States)

    2007-11-02

    Mr Dawkins , has boldly declared that the issue is no longer about uranium mining or now mining but about "how best you might arrange for the...components so as to guarantee that the agreement will be implemented on a limited basis." Richard Kennedy, a responsible person for U.S. nuclear affairs

  4. Worldwide Report, Nuclear Development and Proliferation

    Science.gov (United States)

    2007-11-02

    Spanish 0102 GMT 14 Nov 84] NUCLEAR ENERGY GROWTH—The minister of public works and services, engineer Roque Carranza , stated that the government is...dispenses with fossil fuels. Engineer Carranza explained that, during the first 9 months of this year, consumption of energy grew about 5 percent while

  5. Safety and effective developing nuclear power to realize green and low-carbon development

    Directory of Open Access Journals (Sweden)

    Qi-Zhen Ye

    2016-03-01

    Full Text Available This paper analyzes the role of nuclear power of China's energy structure and industry system. Comparing with other renewable energy the nuclear power chain has very low greenhouse gas emission, so it will play more important role in China's low-carbon economy. The paper also discussed the necessity of nuclear power development to achieve emission reduction, energy structure adjustment, nuclear power safety, environmental protection, enhancement of nuclear power technology, nuclear waste treatment, and disposal, as well as nuclear power plant decommissioning. Based on the safety record and situation of the existing power plants in China, the current status of the development of world nuclear power technology, and the features of the independently designed advanced power plants in China, this paper aims to demonstrate the safety of nuclear power. A nuclear power plant will not cause harm either to the environment and nor to the public according to the real data of radioactivity release, which are obtained from an operational nuclear plant. The development of nuclear power technology can enhance the safety of nuclear power. Further, this paper discusses issues related to the nuclear fuel cycle, the treatment, and disposal strategies of nuclear waste, and the decommissioning of a nuclear power plant, all of which are issues of public concern.

  6. 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).

  7. US develops neutron to sniff out nuclear material

    CERN Multimedia

    2002-01-01

    The USA has developed a tiny portable neutron device that can detect hidden nuclear materials. The device is undergoing trials in the Argonne National Laboratory to see if it could be used to stop smuggling and unauthorised use of nuclear weapons and materials (1/2 page).

  8. Nuclear Waste Disposal: A Cautionary Tale for Shale Gas Development

    Science.gov (United States)

    Alley, William M.; Cherry, John A.; Parker, Beth L.; Ryan, M. Cathryn

    2014-07-01

    Nuclear energy and shale gas development each began with the promise of cheap, abundant energy and prospects for national energy independence. Nuclear energy was touted as "too cheap to meter," and shale gas promised jobs and other economic benefits during a recession.

  9. Bimodal Nuclear Thermal Rocket Analysis Developments

    Science.gov (United States)

    Belair, Michael; Lavelle, Thomas; Saimento, Charles; Juhasz, Albert; Stewart, Mark

    2014-01-01

    Nuclear thermal propulsion has long been considered an enabling technology for human missions to Mars and beyond. One concept of operations for these missions utilizes the nuclear reactor to generate electrical power during coast phases, known as bimodal operation. This presentation focuses on the systems modeling and analysis efforts for a NERVA derived concept. The NERVA bimodal operation derives the thermal energy from the core tie tube elements. Recent analysis has shown potential temperature distributions in the tie tube elements that may limit the thermodynamic efficiency of the closed Brayton cycle used to generate electricity with the current design. The results of this analysis are discussed as well as the potential implications to a bimodal NERVA type reactor.

  10. Ongoing Space Nuclear Systems Development in the United States

    Energy Technology Data Exchange (ETDEWEB)

    S. Bragg-Sitton; J. Werner; S. Johnson; Michael G. Houts; Donald T. Palac; Lee S. Mason; David I. Poston; A. Lou Qualls

    2011-10-01

    Reliable, long-life power systems are required for ambitious space exploration missions. Nuclear power and propulsion options can enable a bold, new set of missions and introduce propulsion capabilities to achieve access to science destinations that are not possible with more conventional systems. Space nuclear power options can be divided into three main categories: radioisotope power for heating or low power applications; fission power systems for non-terrestrial surface application or for spacecraft power; and fission power systems for electric propulsion or direct thermal propulsion. Each of these areas has been investigated in the United States since the 1950s, achieving various stages of development. While some nuclear systems have achieved flight deployment, others continue to be researched today. This paper will provide a brief overview of historical space nuclear programs in the U.S. and will provide a summary of the ongoing space nuclear systems research, development, and deployment in the United States.

  11. Collaborative development of Estonian nuclear master's program

    Energy Technology Data Exchange (ETDEWEB)

    Tkaczyk, A. H.; Kikas, A.; Realo, E.; Kirm, M.; Kiisk, M.; Isakar, K.; Suursoo, S.; Koch, R.; Feldbach, E.; Lushchik, A.; Reivelt, K. [Inst. of Physics, Univ. of Tartu, Riia 142, Tartu 51014 (Estonia)

    2012-07-01

    In 2009 Estonia approved the National Development Plan for the Energy Sector, including the nuclear energy option. This can be realized by construction of a nuclear power plant (NPP) in Estonia or by participation in neighboring nuclear projects (e.g., Lithuania and/or Finland). Either option requires the availability of competent personnel. It is necessary to prepare specialists with expertise in all aspects related to nuclear infrastructure and to meet workforce needs (e.g. energy enterprises, public agencies, municipalities). Estonia's leading institutions of higher education and research with the support of the European Social Fund have announced in this context a new nuclear master's curriculum to be developed. The language of instruction will be English. (authors)

  12. Development of Scintillators in Nuclear Medicine.

    Science.gov (United States)

    Khoshakhlagh, Mohammad; Islamian, Jalil Pirayesh; Abedi, Seyed Mohammad; Mahmoudian, Babak

    2015-01-01

    High-quality image is necessary for accurate diagnosis in nuclear medicine. There are many factors in creating a good image and detector is the most important one. In recent years, several detectors are studied to get a better picture. The aim of this paper is comparison of some type of these detectors such as thallium activated sodium iodide bismuth germinate cesium activated yttrium aluminum garnet (YAG: Ce) YAP: Ce "lutetium aluminum garnet activated by cerium" CRY018 "CRY019" lanthanum bromide and cadmium zinc telluride. We studied different properties of these crystals including density, energy resolution and decay times that are more important factors affecting the image quality.

  13. Nuclear Human Resources Development Program using Educational Core Simulator

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Yu Sun; Hong, Soon Kwan [KHNP-CRI, Daejeon (Korea, Republic of)

    2015-10-15

    KHNP-CRI(Korea Hydro and Nuclear Power Co.-Central Research Institute) has redesigned the existing Core Simulator(CoSi) used as a sort of training tools for reactor engineers in operating nuclear power plant to support Nuclear Human Resources Development (NHRD) Program focusing on the nuclear department of Dalat university in Vietnam. This program has been supported by MOTIE in Korea and cooperated with KNA(Korea Nuclear Association for International Cooperation) and HYU(Hanyang University) for enhancing the nuclear human resources of potential country in consideration with Korean Nuclear Power Plant as a next candidate energy sources. KHNP-CRI has provided Edu-CoSi to Dalat University in Vietnam in order to support Nuclear Human Resources Development Program in Vietnam. Job Qualification Certificates Program in KHNP is utilized to design a training course for Vietnamese faculty and student of Dalat University. Successfully, knowhow on lecturing the ZPPT performance, training and maintaining Edu-CoSi hardware are transferred by several training courses which KHNP-CRI provides.

  14. Nuclear power program and technology development in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Byung-Oke

    1994-12-31

    KEPCO has successfully implemented the construction and operation of nuclear power plants since the early 1970s, and will continue to build safer and more efficient nuclear plants in the future in accordance with the nuclear power development plan previously established. KEPCO will also make every effort to enhance nuclear safety and obtain the public`s acceptance for nuclear power. We are, however, facing the same difficulties, as United States and other countries have, in strengthened regulatory requirements, public acceptance, radwaste disposal, and acquisition of new plant sites despite an active nuclear power program. Story of Ted Turner, CNN; {open_quotes}It ain`t as easy as it looks.{close_quotes} Yes! It is difficult. But we will cope with these issues so that we can promote the nuclear power development and continue to supply a highly economical and clean energy to the world. In this regard, it is my sincere wish that each organization participating in the nuclear industry, especially Korea and United States strengthen their ties and help each other so that we together can successfully accomplish our goals.

  15. Department of Energy: Nuclear S&T workforce development programs

    Energy Technology Data Exchange (ETDEWEB)

    Bingham, Michelle [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bala, Marsha [Idaho National Lab. (INL), Idaho Falls, ID (United States); Beierschmitt, Kelly [Idaho National Lab. (INL), Idaho Falls, ID (United States); Steele, Carolyn [Argonne National Lab. (ANL), Argonne, IL (United States); Sattelberger, Alfred P. [Argonne National Lab. (ANL), Argonne, IL (United States); Bruozas, Meridith A. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-01-01

    The U.S. Department of Energy (DOE) national laboratories use their expertise in nuclear science and technology (S&T) to support a robust national nuclear S&T enterprise from the ground up. Traditional academic programs do not provide all the elements necessary to develop this expertise, so the DOE has initiated a number of supplemental programs to develop and support the nuclear S&T workforce pipeline. This document catalogs existing workforce development programs that are supported by a number of DOE offices (such as the Offices of Nuclear Energy, Science, Energy Efficiency, and Environmental Management), and by the National Nuclear Security Administration (NNSA) and the Naval Reactor Program. Workforce development programs in nuclear S&T administered through the Department of Homeland Security, the Nuclear Regulatory Commission, and the Department of Defense are also included. The information about these programs, which is cataloged below, is drawn from the program websites. Some programs, such as the Minority Serving Institutes Partnership Programs (MSIPPs) are available through more than one DOE office, so they appear in more than one section of this document.

  16. Appliance of software engineering in development of nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Baek, Y. W.; Kim, H. C.; Yun, C. [Chungnam National Univ., Taejon (Korea, Republic of); Kim, B. R. [KINS, Taejon (Korea, Republic of)

    1999-10-01

    Application of computer technology in nuclear power plant is also a necessary transformation as in other industry fields. But until now, application of software technology was not wide-spread because of its potential effect to safety in nuclear field. It is an urgent theme to develop evaluation guide and regulation techniques to guarantee safety, reliability and quality assurance. To meet these changes, techniques for development and operation should be enhanced to ensure the quality of software systems. In this study, we show the difference between waterfall model and software life-cycle needed in development of nuclear power plant and propose the consistent framework needed in development of instrumentation and control system of nuclear power plant.

  17. Nuclear power development in the Eighties

    Energy Technology Data Exchange (ETDEWEB)

    Ibe, L.D.

    1974-01-01

    Plans to accelerate the nation-wide rural electrification program and tap energy sources to reduce dependency on oil-fired plants to reasonably low levels within the decade in the Philippines were announced. The specific goals of the National Energy Plan are: the reduction of the country's oil dependency for its total energy needs from the present high 93 percent to 76 percent by 1985; for power generation, the contribution of oil-fired power plants to be reduced from the present level of 75 percent to 37 percent by 1985; and for other energy uses, 15 percent to 20 percent savings through conservation measures and improvements in energy utilization efficiency. The Energy Plan aims at a balanced contribution from hydro, conventional thermal, geothermal, and nuclear plants by 1990. Plans for the power generation expansion program by the National Power Corporation (NPC) are described for the Luzon, Mindanao, and Visayas regions. It is concluded that the National Energy Plan and the NPC program encompass: no additional oil-fired generating units except for those planned or ordered; geothermal and nuclear power stations will provide energy for future base load operations; and hydro installation will provide peaking needs. (MCW)

  18. Hyperthermal Environments Simulator for Nuclear Rocket Engine Development

    Science.gov (United States)

    Litchford, Ron J.; Foote, John P.; Clifton, W. B.; Hickman, Robert R.; Wang, Ten-See; Dobson, Christopher C.

    2011-01-01

    An arc-heater driven hyperthermal convective environments simulator was recently developed and commissioned for long duration hot hydrogen exposure of nuclear thermal rocket materials. This newly established non-nuclear testing capability uses a high-power, multi-gas, wall-stabilized constricted arc-heater to produce hightemperature pressurized hydrogen flows representative of nuclear reactor core environments, excepting radiation effects, and is intended to serve as a low-cost facility for supporting non-nuclear developmental testing of hightemperature fissile fuels and structural materials. The resulting reactor environments simulator represents a valuable addition to the available inventory of non-nuclear test facilities and is uniquely capable of investigating and characterizing candidate fuel/structural materials, improving associated processing/fabrication techniques, and simulating reactor thermal hydraulics. This paper summarizes facility design and engineering development efforts and reports baseline operational characteristics as determined from a series of performance mapping and long duration capability demonstration tests. Potential follow-on developmental strategies are also suggested in view of the technical and policy challenges ahead. Keywords: Nuclear Rocket Engine, Reactor Environments, Non-Nuclear Testing, Fissile Fuel Development.

  19. Nuclear thermal propulsion test facility requirements and development strategy

    Science.gov (United States)

    Allen, George C.; Warren, John; Clark, J. S.

    1991-01-01

    The Nuclear Thermal Propulsion (NTP) subpanel of the Space Nuclear Propulsion Test Facilities Panel evaluated facility requirements and strategies for nuclear thermal propulsion systems development. High pressure, solid core concepts were considered as the baseline for the evaluation, with low pressure concepts an alternative. The work of the NTP subpanel revealed that a wealth of facilities already exists to support NTP development, and that only a few new facilities must be constructed. Some modifications to existing facilities will be required. Present funding emphasis should be on long-lead-time items for the major new ground test facility complex and on facilities supporting nuclear fuel development, hot hydrogen flow test facilities, and low power critical facilities.

  20. Nuclear thermal propulsion test facility requirements and development strategy

    Science.gov (United States)

    Allen, George C.; Clark, John S.; Warren, John; Perkins, David R.; Martinell, John

    1992-01-01

    The Nuclear Thermal Propulsion (NTP) subpanel of the Space Nuclear Propulsion Test Facilities Panel evaluated facility requirements and strategies for nuclear thermal propulsion systems development. High pressure, solid core concepts were considered as the baseline for the evaluation, with low pressure concepts an alternative. The work of the NTP subpanel revealed that a wealth of facilities already exists to support NTP development, and that only a few new facilities must be constructed. Some modifications to existing facilities will be required. Present funding emphasis should be on long-lead-time items for the major new ground test facility complex and on facilities supporting nuclear fuel development, hot hydrogen flow test facilities, and low power critical facilities.

  1. Nuclear safety culture in Finland and Sweden - Developments and challenges

    Energy Technology Data Exchange (ETDEWEB)

    Reiman, T.; Pietikaeinen, E. (Technical Research Centre of Finland, VTT (Finland)); Kahlbom, U. (RiskPilot AB (Sweden)); Rollenhagen, C. (Royal Institute of Technology (KTH) (Sweden))

    2011-02-15

    The project aimed at studying the concept of nuclear safety culture and the Nordic nuclear branch safety culture. The project also aimed at looking how the power companies and the regulators view the current responsibilities and role of subcontractors in the Nordic nuclear safety culture as well as to inspect the special demands for safety culture in subcontracting chains. Interview data was collected in Sweden (n = 14) and Finland (n = 16) during 2009. Interviewees represented the major actors in the nuclear field (regulators, power companies, expert organizations, waste management organizations). Results gave insight into the nature and evaluation of safety culture in the nuclear industry. Results illustrated that there is a wide variety of views on matters that are considered important for nuclear safety within the Nordic nuclear community. However, the interviewees considered quite uniformly such psychological states as motivation, mindfulness, sense of control, understanding of hazards and sense of responsibility as important for nuclear safety. Results also gave insight into the characteristics of Nordic nuclear culture. Various differences in safety cultures in Finland and Sweden were uncovered. In addition to the differences, historical reasons for the development of the nuclear safety cultures in Finland and Sweden were pointed out. Finally, results gave implications that on the one hand subcontractors can bring new ideas and improvements to the plants' practices, but on the other hand the assurance of necessary safety attitudes and competence of the subcontracting companies and their employees is considered as a challenge. The report concludes that a good safety culture requires a deep and wide understanding of nuclear safety including the various accident mechanisms of the power plants as well as a willingness to continuously develop one's competence and understanding. An effective and resilient nuclear safety culture has to foster a constant

  2. Development of life evaluation technology for nuclear power plant components

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; Kim, Yun Jae; Choi, Jae Boong [Sungkyunkwan Univ., Seoul (Korea, Republic of)] (and others)

    2002-03-15

    This project focuses on developing reliable life evaluation technology for nuclear power plant components, and is divided into two parts, development of a life evaluation system for nuclear pressure vessels and evaluation of applicability of emerging technology to operating plants. For the development of life evaluation system for nuclear pressure vessels, the following seven topics are covered in this project: defect assessment method for steam generator tubes, development of fatigue monitoring system, assessment of corroded pipes, domestic round robin analysis for constructing P-T limit curve for RPV, development of probabilistic integrity assessment technique, effect of aging on strength of dissimilar welds, applicability of LBB to cast stainless steel, and development of probabilistic piping fracture mechanics.

  3. Development of a Pedestrian Special Nuclear Material Radiation Monitor

    Institute of Scientific and Technical Information of China (English)

    2001-01-01

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

  4. Recommendations on Strengthening the Development of Nuclear Medicine in China

    Institute of Scientific and Technical Information of China (English)

    Shih-chen Wang

    2009-01-01

    @@ This paper outlines briefly the role of nuclear medicine in life sciences and health care. Molecular imaging by using isotopic tracers can noninvasively visualize the chemistry or hidden process in the cells and tissues inside the body, obtaining "functional" images to provide early information of any disease and revealing the secrets of life. The vitality of nuclear medicine is its ability to translate bench into new clinical application that can benefits the patients. Although nuclear medicine community in China has made significant achievement with a great effort since 1950s, there are many obstacles to future development. Recommended measures are proposed here in an attempt to solve our existing problems.

  5. Developing a Nuclear Global Health Workforce Amid the Increasing Threat of a Nuclear Crisis.

    Science.gov (United States)

    Burkle, Frederick M; Dallas, Cham E

    2016-02-01

    This study argues that any nuclear weapon exchange or major nuclear plant meltdown, in the categories of human systems failure and conflict-based crises, will immediately provoke an unprecedented public health emergency of international concern. Notwithstanding nuclear triage and management plans and technical monitoring standards within the International Atomic Energy Agency and the World Health Organization (WHO), the capacity to rapidly deploy a robust professional workforce with the internal coordination and collaboration capabilities required for large-scale nuclear crises is profoundly lacking. A similar dilemma, evident in the early stages of the Ebola epidemic, was eventually managed by using worldwide infectious disease experts from the Global Outbreak Alert and Response Network and multiple multidisciplinary WHO-supported foreign medical teams. This success has led the WHO to propose the development of a Global Health Workforce. A strategic format is proposed for nuclear preparedness and response that builds and expands on the current model for infectious disease outbreak currently under consideration. This study proposes the inclusion of a nuclear global health workforce under the technical expertise of the International Atomic Energy Agency and WHO's Radiation Emergency Medical Preparedness and Assistance Network leadership and supported by the International Health Regulations Treaty. Rationales are set forth for the development, structure, and function of a nuclear workforce based on health outcomes research that define the unique health, health systems, and public health challenges of a nuclear crisis. Recent research supports that life-saving opportunities are possible, but only if a rapidly deployed and robust multidisciplinary response component exists.

  6. Nuclear Explosion Monitoring History and Research and Development

    Science.gov (United States)

    Hawkins, W. L.; Zucca, J. J.

    2008-12-01

    Within a year after the nuclear detonations over Hiroshima and Nagasaki the Baruch Plan was presented to the newly formed United Nations Atomic Energy Commission (June 14, 1946) to establish nuclear disarmament and international control over all nuclear activities. These controls would allow only the peaceful use of atomic energy. The plan was rejected through a Security Council veto primarily because of the resistance to unlimited inspections. Since that time there have been many multilateral, and bilateral agreements, and unilateral declarations to limit or eliminate nuclear detonations. Almost all of theses agreements (i.e. treaties) call for some type of monitoring. We will review a timeline showing the history of nuclear testing and the more important treaties. We will also describe testing operations, containment, phenomenology, and observations. The Comprehensive Nuclear Test Ban Treaty (CTBT) which has been signed by 179 countries (ratified by 144) established the International Monitoring System global verification regime which employs seismic, infrasound, hydroacoustic and radionuclide monitoring techniques. The CTBT also includes on-site inspection to clarify whether a nuclear explosion has been carried out in violation of the Treaty. The US Department of Energy (DOE) through its National Nuclear Security Agency's Ground-Based Nuclear Explosion Monitoring R&D Program supports research by US National Laboratories, and universities and industry internationally to detect, locate, and identify nuclear detonations. This research program builds on the broad base of monitoring expertise developed over several decades. Annually the DOE and the US Department of Defense jointly solicit monitoring research proposals. Areas of research include: seismic regional characterization and wave propagation, seismic event detection and location, seismic identification and source characterization, hydroacoustic monitoring, radionuclide monitoring, infrasound monitoring, and

  7. NNSA Program Develops the Next Generation of Nuclear Security Experts

    Energy Technology Data Exchange (ETDEWEB)

    Brim, Cornelia P.; Disney, Maren V.

    2015-09-02

    NNSA is fostering the next generation of nuclear security experts is through its successful NNSA Graduate Fellowship Program (NGFP). NGFP offers its Fellows an exceptional career development opportunity through hands-on experience supporting NNSA mission areas across policy and technology disciplines. The one-year assignments give tomorrow’s leaders in global nuclear security and nonproliferation unparalleled exposure through assignments to Program Offices across NNSA.

  8. Scientific codes developed and used at GRS. Nuclear simulation chain

    Energy Technology Data Exchange (ETDEWEB)

    Schaffrath, Andreas; Sonnenkalb, Martin; Sievers, Juergen; Luther, Wolfgang; Velkov, Kiril [Gesellschaft fuer Anlagen und Reaktorsicherheit (GRS) gGmbH, Garching/Muenchen (Germany). Forschungszentrum

    2016-05-15

    Over 60 technical experts of the reactor safety research division of the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH are developing and validating reliable methods and computer codes - summarized under the term nuclear simulation chain - for the safety-related assessment for all types of nuclear power plants (NPP) and other nuclear facilities considering the current state of science and technology. This nuclear simulation chain has to be able to simulate and assess all relevant physical processes and phenomena for all operating states and (severe) accidents. In the present contribution, the nuclear simulation chain developed and applied by GRS as well as selected examples of its application are presented. The latter demonstrate impressively the width of its scope and its performance. The GRS codes can be passed on request to other (national as well as international) organizations. This contributes to a worldwide increase of the nuclear safety standards. The code transfer is especially important for developing and emerging countries lacking the financial means and/or the necessary know-how for this purpose. At the end of this contribution, the respective course of action is described.

  9. Nuclear energy system for sustainable development of mankind

    Energy Technology Data Exchange (ETDEWEB)

    Fuji-ie, Yoichi [Hiroshima Univ., Tokyo (Japan)

    2009-04-15

    The former principle is attributable to the fact that Japan is the only country in the world who suffered atomic bombing not only in Hiroshima but also in Nagasaki. The tragedies imbued the Japanese with opposition to atomic bombs. The latter is that the sentiment to oppose the misery of war is one of the factors that have led the Japanese to the peaceful use of nuclear energy, since it is subject to fewer have led the Japanese to the peaceful use of nuclear energy, since it is subject to fewer resource limitations and thereby enables the Japanese to secure energy peacefully without causing troubles to other countries. We have kept the basic nuclear policy and developed nuclear science and technology. The fruits of the development can be seen both in nuclear power generation as well as radiation application to various areas of Japanese society. In addition to these two principles The Atomic Energy Basic Law of Japan states also contribution to international community through nuclear research and development.

  10. Development of nuclear reaction data retrieval system on Meme media

    Energy Technology Data Exchange (ETDEWEB)

    Ohbayasi, Yosihide; Masui, Hiroshi [Meme Media Lab., Hokkaido Univ., Sapporo (Japan); Aoyama, Shigeyoshi [Information Processing Center, Kitami Inst. of Tech., Hokkaido (Japan); Kato, Kiyoshi [Graduate School of Science, Hokkaido Univ., Sapporo (Japan); Chiba, Masaki [Division of Social Information, Sapporo Gakuin Univ., Ebetsu, Hokkaido (Japan)

    2000-03-01

    A newly designed retrieval system of charged particle nuclear reaction data is developed on Meme media architecture. We designed the network-based (client-server) retrieval system. The server system is constructed on a UNIX workstation with a relational database, and the client system is constructed on Microsoft Windows PC using an IntelligentPad software package. The IntelligentPad is currently available as developing Meme media. We will develop the system to realize effective utilization of nuclear reaction data: I. 'Re-production, Re-edit, Re-use', II. 'Circulation, Coordination and Evolution', III. 'Knowledge discovery'. (author)

  11. Global Nuclear Energy Partnership Technology Development Plan

    Energy Technology Data Exchange (ETDEWEB)

    David J. Hill

    2007-07-01

    This plan describes the GNEP Technology Demonstration Program (GNEP-TDP). It has been prepared to guide the development of integrated plans and budgets for realizing the domestic portion of the GNEP vision as well as providing the basis for developing international cooperation. Beginning with the GNEP overall goals, it describes the basic technical objectives for each element of the program, summarizes the technology status and identifies the areas of greatest technical risk. On this basis a proposed technology demonstration program is described that can deliver the required information for a Secretarial decision in the summer of 2008 and support construction of facilities.

  12. Developing the nuclear idea: concept, technique, and process.

    Science.gov (United States)

    Billow, Richard M

    2013-10-01

    I introduce an approach to group that has remained undeveloped in the literature, but represents an essence of relationally oriented group psychotherapy. Evolving from the verbalizations and enactments through which the group symbolizes and becomes known-a nuclear idea takes shape. It emerges from the nucleus of the group process: co-created from intersubjective forces and locations that cannot be fully specified, yet may be possible to observe, name, and utilize clinically. Groups organize themselves by developing nuclear ideas, with the therapist's active participation. They are vehicles through which a group comes to think about its thinking: not only what it thinks, but also how it thinks, or chooses not to think, and when and why. Developing the nuclear idea provides a framework for how the therapist-and the group itself-goes about the task of containing. With its emphasis on meaning and the development of meaning as transformational, the concept of the nuclear idea supplements the whole group, interpersonal, and intrapsychic lenses through which the therapist comes to understand group experience and base interventions. Clinical vignettes illustrate how the therapist may develop nuclear ideas thematically, conceptualize further, and negotiate meaning with the co-participation of other group members.

  13. Type Selection for Present Nuclear Power Development in China

    Institute of Scientific and Technical Information of China (English)

    Gu Junyang; Shi Wenbao; Ye Qing

    2006-01-01

    With rapid development of nuclear power in China, in view of reactor type selection, this paper analyzes the current situation that faces nuclear power industry, the technical characteristics of optional reactors and the tendency of nuclear power technology development in the future. The proposals put forward in this paper include choosing and introducing GW-class advanced PWR as main reactors, carrying out self-supporting projects and technical transfer negotiations, in addition, promoting the design of the advanced generation-Ⅱ PWR and initiating small-scaled construction. The ultimate target is to catch up with the world advanced level by means of technical upgrading and recreation based on technology importation and assimilation.

  14. A Study on Human Resources Development in Nuclear Field

    Energy Technology Data Exchange (ETDEWEB)

    Moon, Keehwan; Lee, M. K.; Kim, S. S.; Nam, J. H.; Won, B. C.; Lee, D. S; Hwang, I. A.; Seo, M. W.

    2011-11-15

    The study encompasses 4 major parts, each results being described here under: Various policy alternatives through supply-demand analysis of domestic nuclear skilled manpower are suggested. Human resources development programs of main educational organizations in domestic and overseas are comprehensively reviewed. Establishment of 'Integrated Management Organization' which can combine and manage domestic educational organizations' educational functions is necessary to efficiently deal with the increased educational demand and the shift of educational paradigm from supply-driven to needs-driven education and to make nuclear energy export sustainable. And road map on human resource development to efficiently accomplish 'Integrated Management Organization's mission is suggested. It is provided that an overall strategies for the reasonable educational program reflecting the good practices with their implications in overseas nuclear education programs.

  15. 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.

  16. Hyperthermal Environments Simulator for Nuclear Rocket Engine Development

    Science.gov (United States)

    Litchford, R. J.; Foote, J. P.; Clifton, W. B.; Hickman, R. R.; Wang, T.-S.; Dobson, C. C.

    An arc-heater driven hyperthermal convective environments simulator was recently developed and commissioned for long duration hot hydrogen exposure of nuclear thermal rocket materials. This newly established non-nuclear testing capability uses a high-power, multi-gas, wall-stabilised constricted arc-heater to produce high-temperature pressurised hydrogen flows representative of nuclear reactor core environments, excepting radiation effects, and is intended to serve as a low-cost facility for supporting non-nuclear developmental testing of high-temperature fissile fuels and structural materials. The resulting reactor environments simulator represents a valuable addition to the available inventory of non-nuclear test facilities and is uniquely capable of investigating and characterising candidate fuel/structural materials, improving associated processing/ fabrication techniques, and simulating reactor thermal hydraulics. This paper summarizes facility design and engineering development efforts and reports baseline operational characteristics as determined from a series of performance mapping and long duration capability demonstration tests. Potential follow-on developmental strategies are also suggested in view of the technical and policy challenges ahead.

  17. Robotic control architecture development for automated nuclear material handling systems

    Energy Technology Data Exchange (ETDEWEB)

    Merrill, R.D.; Hurd, R.; Couture, S.; Wilhelmsen, K.

    1995-02-01

    Lawrence Livermore National Laboratory (LLNL) is engaged in developing automated systems for handling materials for mixed waste treatment, nuclear pyrochemical processing, and weapon components disassembly. In support of these application areas there is an extensive robotic development program. This paper will describe the portion of this effort at LLNL devoted to control system architecture development, and review two applications currently being implemented which incorporate these technologies.

  18. Development of the Experimental Photo-Nuclear Reaction Database in Hokkaido University

    Science.gov (United States)

    Makinaga, A.

    2015-10-01

    Nuclear databases are important tools to apply nuclear phenomena to various fields of nuclear engineering. It is now recognized that the databases must be further developed for photo-nuclear reaction data for nuclear security, safety and nonproliferation applications. Hokkaido University Nuclear Reaction Data Centre (JCPRG) has contributed to the Experimental Nuclear Reaction Data Library (EXFOR) which is developed by the International Network of Nuclear Reaction Data Centres under coordination by IAEA. We report here on the recent compilation of the nuclear data files for the photonuclear reaction.

  19. Development of TSC SAMG for Nuclear Power Reactor

    Institute of Scientific and Technical Information of China (English)

    HUANGDong-xing; PUSheng-di; ZHAOShou-zhi; LIJi-gen

    2003-01-01

    Severe Accident Management Guidance (SAMG) is developed to prevent the severe accident progress and mitigate the consequences of severe accident in nuclear power plant. Technical Support Center (TSC) SAMG is one of important components of the strategies. It contains Severe Accident Guidelines (SAGs) and Severe Challenge Guidelines (SCGs).

  20. Development of nuclear power plant real-time engineering simulator

    Institute of Scientific and Technical Information of China (English)

    LIN Meng; YANG Yan-Hua; ZHANG Rong-Hua; HU Rui

    2005-01-01

    A nuclear power plant real-time engineering simulator was developed based on general-purpose thermal-hydraulic system simulation code RELAP5. It main1y consists of three parts: improved thermal-hydraulic system simulation code RELAP5, control and protection system and human-machine interface. A normal transient of CHASHMA nuclear power plant turbine step load change from 100% to 90% of full power, was simulated by the engineering simulator as an application example. This paper presents structure and main features of the engineering simulator, and application results are shown and discussed.

  1. Development of life evaluation technology for nuclear power plant components

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin [Sungkyunkwan Univ., Seoul (Korea, Republic of); Kwon, J. D. [Yeungnam Univ., Gyeongsan (Korea, Republic of); Kang, K. J. [Chonnam National Univ., Gwangju (Korea, Republic of)] (and others)

    2001-03-15

    This research focuses on development of reliable life evaluation technology for nuclear power plant (NPP) components, and is divided into two parts, development of life evaluation systems for pressurized components and evaluation of applicability of emerging technology to operating plants. For the development of life evaluation system for nuclear pressure vessels, the following seven topics are covered: development of expert systems for integrity assessment of pressurized components, development of integrity evaluation systems of steam generator tubes, prediction of failure probability for NPP components based on probabilistic fracture mechanics, development of fatigue damage evaluation technique for plant life extension, domestic round robin analysis for pressurized thermal shock of reactor vessels, domestic round robin analysis of constructing P--T limit curves for reactor vessels, and development of data base for integrity assessment. For evaluation of applicability of emerging technology to operating plants, on the other hand, the following eight topics are covered: applicability of the Leak-Before-Break analysis to Cast S/S piping, collection of aged material tensile and toughness data for aged Cast S/S piping, finite element analyses for load carrying capacity of corroded pipes, development of Risk-based ISI methodology for nuclear piping, collection of toughness data for integrity assessment of bi-metallic joints, applicability of the Master curve concept to reactor vessel integrity assessment, measurement of dynamic fracture toughness, and provision of information related to regulation and plant life extension issues.

  2. Development of Nuclear Control and Management Information Treatment System

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, J. G.; Lee, B. D.; So, D. S. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2007-07-01

    To implement obligations under the Non-Proliferation Treaty (NPT) and the bilateral agreements more effectively, we proposed a computerized system named the Nuclear Control and Management Information Treatment System (NCAMITS) as a part of the Nuclear Transparency Enhancement Project at the Korea Atomic Energy Research Institute (KAERI). The database system is designed not only to undertake the facility-level accounting for and control of nuclear material at KAERI, but also to meet the requirements of the State (National) System of Accounting and Control (SSAC). Since the NCAMITS will provide services for the facility operators as well as the safeguard information managers at KAERI, the development of the system is supposed to accommodate the end-user's convenience and the manager's sophisticated specifications as well.

  3. Development of a quality management system for Brazilian nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    Kibrit, Eduardo [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), Sao Paulo, SP (Brazil). Dept. da Qualidade]. E-mail: edkibrit@yahoo.com.br; Zouain, Desiree Moraes [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil). Div. de Planejamento e Inovacao Tecnologica]. E-mail: dmzouain@ipen.br

    2005-07-01

    The present work is a proposal for developing a quality management system for Brazilian nuclear installations, based on applicable standards. The standard ISO 9001:2000 [4] establishes general requirements for the implementation of a quality management system in all kinds of organizations. The standard IAEA 50-C/SG-Q [1] establishes general requirements for the implementation of a quality assurance system in nuclear installations. The standard CNEN-NN- 1.16 [5] establishes the regulating requirements for the quality assurance systems and programs of nuclear installations, for licensing and authorization for operation of these installations in Brazil. The revision of standard IAEA 50-C/SG-Q [1], to be replaced by IAEA DS 338 [2] and IAEA DPP 349 [3], introduces the concept of 'Integrated Management System' for the nuclear area, in preference to the concept of 'Quality Assurance'. This approach is incorporated with the current tendency, because it guides the system to manage, in an integrated way, the requirements of quality, safety, health, environment, security and economics of the installation. The results of the characterization of the quality management systems established in the applicable standards are presented, with the determination of the common and conflicting points among them. Referring data to quality assurance program/quality management system in some nuclear installations of IAEA Member States are also presented. (author)

  4. Technology development for nuclear material measurement and accountability

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Jong Sook; Lee, Byung Doo; Cha, Hong Ryul; Lee, Yong Duk; Choi, Hyung Nae; Nah, Won Woo; Park, Hoh Joon; Lee, Yung Kil [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-12-01

    The measurement techniques for Pu samples and spent fuel assembly were developed in support of the implementation of national inspection responsibility under the Atomic Energy Act promulgated in 1994 and a computer program was also developed to assess the total nuclear material balance by facility declared records. The results of plutonium isotopic determination by gamma-ray spectrometry with high resolution germanium detector with peak analysis codes (FRAM and MGA codes) were approached to within 1% {approx} 2% of error from chemical analysis values by mass spectrometry. A gamma-ray measurement system for underwater spent nuclear fuels was developed and tested successfully. The falsification of facility and state records can be traced with the help of the developed computer code against declared reports submitted by the concerned state. This activity eventually resulted in finding the discrepancy of accountability records. 18 figs, 20 tabs, 27 refs. (Author).

  5. Developing competence based qualification system in the nuclear energy sector

    Energy Technology Data Exchange (ETDEWEB)

    Ceclan, Mihail [European Commission, Petten (Netherlands). Inst. for Energy and Transport

    2016-04-15

    The Institute for Energy and Transport of the Joint Research Centre, European Commission, developed a strategy and road map for ECVET implementation. The JRC road map for European Credit System for Vocational Education and Training (ECVET) implementation has reached the stage of Competence-Based Qualification System development. The Competence-Based Qualification System can help bridge the gap between Human Resources demand and supply in the nuclear market by structuring qualifications in small independent parts. This very specific ECVET feature of a qualification, facilitates the process of competences accumulation and the lifelong learning, mobility and flexible learning pathways. New developments are presented about the Competence-Based Qualification System development for the nuclear energy sector.

  6. Nuclear fuel cycle and sustainable development: strategies for the future

    Energy Technology Data Exchange (ETDEWEB)

    Bouchard, J

    2004-07-01

    In this presentation, the author aims to define the major role of the nuclear energy in the future, according a sustainable development scenario. The today aging park and the new Generation IV technologies are presented. The transition scenario from Pu mono-recycling in PWRs to actinide global recycling in fast neutron Gen IV systems is also developed. Closed cycles and fast reactors appear as the appropriate answer to sustainable objectives in a vision of a large expansion. (A.L.B.)

  7. Hydro and nuclear power for African less-carbon development

    Energy Technology Data Exchange (ETDEWEB)

    El-Gazzar, Mohamed; Ibrahim, Yassin Mohamed; Bedrous, Maher Aziz

    2007-07-01

    Though the overall picture reveal availability of enormous energy resources which far exceed energy requirements of Africa, most of these resources are grossly underutilized, particularly hydro and nuclear resources. It suggests that Africa's problem is not lack of energy resources but its development and utilization. The region will remain a major net exporter of energy for several decades to com. In dealing with its energy problems Africa faces a unique set of initial conditions, defined mainly by its level and pattern of economic growth, social and demographic characteristics, energy resource endowment, location distances between supply sources and consumption areas, technological underdevelopment, and poverty-driven energy-environment conflict. A key challenge is the optimal utilization of the Africa's energy resources to facilitate both individual country and regional energy and economic development. Stronger emphasis on a more integrated energy supply network based on more widespread regional initiatives, particularly in electricity is essential to sustainable energy development in Africa. This paper discusses the prospects for hydro and nuclear power in Africa. The continent is the poorest in the world. The lack of reliable, accessible and affordable energy hinders its development. Hydro and nuclear power promises to be the least-carbon energy sources, while being the cheapest and most reliable among all. The role the hydropower can play in securing a sustainable energy future for Africa is highly emphasized. Also, nuclear power has many advantages to Africa. Opportunities for hydropower and nuclear power in Africa are all considered. Advantages and disadvantages are also all discussed. (auth)

  8. Development of Training Aids for Nuclear Forensics Exercises

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sangjun; Lee, Seungmin; Lim, Hobin; Hyung, Sangcheol; Kim, Jaekwang [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2015-05-15

    Current radioactive-related training has focused on the prevention of a radiation disaster. Procedures to recover nuclear and radiological materials have been simplified due to the lack of training tools to reproduce real conditions for security and staff at nuclear facilities. The process of recovering materials is crucial in order to collect evidence and secure the safety of response forces. Moreover, exercises for recovering lost or missing a low dose radiation sources, does not well match with explosive like RDD blast situations. Therefore KINAC has been developing training aids in order to closely reproduce conditions of an actual terrorist attack and enhance effectiveness of exercises. These tools will be applied to Nuclear Forensics Exercises in which evidence collection is important at the time of an incident. KINAC has been developing training aids to enhance the effectiveness of such exercises by providing simulated conditions of actual terrorist incidents. Simulated training aids, based on the beacon system, operate with electromagnetic waves. These tools are able to simulate environments close to actual conditions by supplying similar properties of radioactivity. Training aids will be helpful in giving experience to security personnel and staff in the event of a terrorist incident. This experience includes collecting evidence for nuclear forensics. KINAC also has a plan to hold drills using these tools this year with The Armed Force CBR Defense Command.

  9. Nuclear and sustainable development; Nucleaire et developpement durable

    Energy Technology Data Exchange (ETDEWEB)

    Audebert, P.; Balle, St.; Barandas, Ch.; Basse-Cathalinat, B.; Bellefontaine, E.; Bernard, H.; Bouhand, M.H.; Bourg, D.; Bourgoignon, F.; Bourlat, Y.; Brunet, F.; Buclet, N.; Buquet, N.; Caron, P.; Cartier, M.; Chagneau, E.; Charles, D.; Chateau, G.; Collette, P.; Collignon, A.; Comtesse, Ch.; Crammer, B.; Dasnias, J.; Decroix, G.; Defoy, B.; Delafontaine, E.; Delcroix, V.; Delerue, X.; Demet, M.; Dimmers, G.; Dodivers, S.; Dubigeon, O.; Eimer, M.; Fadin, H.; Foos, J.; Ganiage, D.; Garraud, J.; Girod, J.P.; Gourod, A.; Goussot, D.; Guignard, C.; Heloury, J.; Hondermarck, B.; Hurel, S.; Jeandron, C.; Josse, A.; Lagon, Ch.; Lalleron, Ch.; Laurent, M.; Legrand, H.; Leveau, E

    2006-07-01

    On September 15. and 16., 2004, at Rene Delcourt invitation, President of the C.L.I. of Paluel and Penly, took place the 4. colloquium of the A.N.C.L.I.. Jean Dasnias, new President of the C.L.I., welcomed the colloquium. Hundred of persons participated. The place of the nuclear power in the energy perspectives of tomorrow, its assets and its weaknesses in front of the other energies and within the framework of a sustainable development, are so many subjects which were discussed. The different tackled subjects are: the stakes in the sustainable development; energy perspectives; the reactors of the fourth generation; nuclear power and transparency; sustainable development and I.R.S.N. (N.C.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Jong Sook; Kim, Ho Dong; Kang, Hee Young; Lee, Young Gil; Byeon, Kee Ho; Park, Young Soo; Cha, Hong Ryul; Park, Ho Joon; Lee, Byung Doo; Chung, Sang Tae; Choi, Hyung Rae; Park, Hyun Soo

    1997-07-01

    During the second phase of research and development program conducted from 1993 to 1996, nuclear material safeguards studies system were performed on the technology development of DUPIC safeguards system such as nuclear material measurement in bulk form and product form, DUPIC fuel reactivity measurement, near-real-time accountancy, and containment and surveillance system for effective and efficient implementation of domestic and international safeguards obligation. By securing in advance a optimized safeguards system with domestically developed hardware and software, it will contribute not only to the effective implementation of DUPIC safeguards, but also to enhance the international confidence build-up in peaceful use of spent fuel material. (author). 27 refs., 13 tabs., 89 figs.

  11. The development of robotic system for the nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seung Ho; Lee, Jae Kyung; Kim, Ki Ho; Jung, Seung Ho; Kim, Chang Hoi; Kim, Byung Soo; Hwang, Suk Yeoung; Seo, Yong Chil; Lee, Young Kwang; Lee, Yong Bum; Kim, Woong Ki; Park, Soon Yong

    1996-07-01

    This project focuses on the development of a heavy-duty telerobotic system (HDTS) and a light-duty mobile robotic system (LDMRS) for use in nuclear power plants. HDTS has been developed for performing tasks such as the installation and removal of nozzle dam inside of water chamber of steam generator. HDTS that is remotely controlled could eliminate or significantly reduce human exposure to hazardous nuclear environment. HDTS has four major subsystems : a 6 degree of freedom master-slave manipulator, a guiding device, a monitoring device and a remote control center. Functional connections of each subsystems has resulted in HDTS that exhibits a high level of dexterity and a broad range of capabilities. LDMRS has been developed to be used in emergency response applications such as monitoring and mapping radiation areas, handling radioactive materials and performing decontamination tasks. LDMRS equipped with four-omnidirectional planetary wheels is capable of ascending and descending stairs by employing a automatic stair climbing algorithm. A force-reflective algorithm developed enables LDMRS to be navigated flat surface with zero turning radius without collision by giving an operator a sense of force. The significance of developments is in providing both HDTS and LDMRS that can be operated from remote locations to perform tasks such as the maintenance of nozzle dam and the video surveillance of the nuclear facilities efficiently and without endangering human workers. This report describes the mechanical design, features, control system, and capabilities of both HDTS and LDMRS. (author). 59 refs., 38 tabs., 132 figs.

  12. Foundational development of an advanced nuclear reactor integrated safety code.

    Energy Technology Data Exchange (ETDEWEB)

    Clarno, Kevin (Oak Ridge National Laboratory, Oak Ridge, TN); Lorber, Alfred Abraham; Pryor, Richard J.; Spotz, William F.; Schmidt, Rodney Cannon; Belcourt, Kenneth (Ktech Corporation, Albuquerque, NM); Hooper, Russell Warren; Humphries, Larry LaRon

    2010-02-01

    This report describes the activities and results of a Sandia LDRD project whose objective was to develop and demonstrate foundational aspects of a next-generation nuclear reactor safety code that leverages advanced computational technology. The project scope was directed towards the systems-level modeling and simulation of an advanced, sodium cooled fast reactor, but the approach developed has a more general applicability. The major accomplishments of the LDRD are centered around the following two activities. (1) The development and testing of LIME, a Lightweight Integrating Multi-physics Environment for coupling codes that is designed to enable both 'legacy' and 'new' physics codes to be combined and strongly coupled using advanced nonlinear solution methods. (2) The development and initial demonstration of BRISC, a prototype next-generation nuclear reactor integrated safety code. BRISC leverages LIME to tightly couple the physics models in several different codes (written in a variety of languages) into one integrated package for simulating accident scenarios in a liquid sodium cooled 'burner' nuclear reactor. Other activities and accomplishments of the LDRD include (a) further development, application and demonstration of the 'non-linear elimination' strategy to enable physics codes that do not provide residuals to be incorporated into LIME, (b) significant extensions of the RIO CFD code capabilities, (c) complex 3D solid modeling and meshing of major fast reactor components and regions, and (d) an approach for multi-physics coupling across non-conformal mesh interfaces.

  13. Material development for India’s nuclear power programme

    Indian Academy of Sciences (India)

    A K Suri

    2013-10-01

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

  14. Personnel involved in nuclear standards development: 1980 directory

    Energy Technology Data Exchange (ETDEWEB)

    Carr, S.J. (ed.)

    1980-03-01

    The development of nuclear standards is an active and necessary endeavor that is concerned with the safe, orderly, and economic development of nuclear potential. There are almost 4100 people from the teachnical community who are presently involved either in writing nuclear standards, including codes, or in the management and processing roles necessary for their approval and promulgation. This document identifies the current participation of each individual as member, chairman, cochairman (vice-chairman), or secretary of about 700 standards development committees and groups. The standards committees and groups are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. This directory includes four major sections: personnel, employers, committees, and a Key-Word-in-Context (KWIC) Index of committee titles. It can also be used to identify the participation of employers as well as to recognize the contributions of individuals to the often interdisciplinary activity of standards development.

  15. The Thai-Canadian nuclear human resources development linkage project

    Energy Technology Data Exchange (ETDEWEB)

    Sumitra, Tatchai; Chankow, Nares [Chulalongkorn university (Thailand); Bradley, K.; Bereznai, G. [Atomic Energy of Canada Limited (Canada)

    1998-07-01

    The Thai-Canadian Nuclear Human Resources Development Linkage Project (the ''Project'') was initiated in 1994 in order to develop the engineering and scientific expertise needed for Thailand to decide whether and how the country can best benefit from the establishment of a nuclear power program. The Project was designed to upgrade current academics and people in industry, and to develop an adequate supply of new technical personnel for academic, industry, utility, regulatory and other government institutions. The key Project objectives included the establishment of a Chair in Nuclear Engineering at Chulalongkorn University, the upgrading of the current Masters level curriculum, the establishment of undergraduate and doctorate level curricula, development and delivery of an industrial training program for people in industry and government, exchanges of Thai and Canadian academics and industry experts to establish common research programs and teaching interests, and a public education program that was to test in Thailand some of the techniques that have been successfully used in Canada. (author)

  16. Development of advanced low alloy steel for nuclear RPV

    Energy Technology Data Exchange (ETDEWEB)

    Lee, H. C.; Shin, K. S.; Lee, S. H.; Lee, B. J. [Seoul National Univ., Seoul (Korea)

    2000-04-01

    Low carbon low alloy steels are used in nuclear power plants as pressure vessel, steam generator, etc. Nuclear pressure vessel material requires good combination of strength/ toughness, good weldability and high resistance to neutron irradiation and corrosion fatigue. For SA508III steels, most widely used in the production of nuclear power plant, attaining toughness is more difficult than strength. When taking into account the loss of toughness due to neutron irradiation, attaining as low transition temperature as possible prior to operation is a critical task in the production of nuclear pressure vessels. In the present study, we investigated detrimental microstructural features of SA508III steels to toughness, then alloy design directions to achieve improved mechanical properties were devised. The next step of alloy design was determined based on phase equilibrium thermodynamics and obtained results. Low carbon low alloy steels having low transition temperatures with enough strength and hardenability were developed. Microstructure and mechanical properties of HAZ of SA508III steels and alloy designed steels were investigated. 22 refs., 147 figs., 38 tabs. (Author)

  17. Development of High Sensitivity Nuclear Emulsion and Fine Grained Emulsion

    Energy Technology Data Exchange (ETDEWEB)

    Kawahara, H.; Asada, T. [Department of Physics, Nagoya University, Nagoya 464-8602 (Japan); Naka, T. [Institute of Advanced Research, Nagoya University (Japan); Naganawa, N.; Kuwabara, K.; Nakamura, M. [Department of Physics, Nagoya University, Nagoya 464-8602 (Japan)

    2014-08-15

    Nuclear emulsion is a particle detector having high spacial resolution and angular resolution. It became useful for large statistics experiment thanks to the development of automatic scanning system. In 2010, a facility for emulsion production was introduced and R and D of nuclear emulsion began at Nagoya university. In this paper, we present results of development of the high sensitivity emulsion and fine grained emulsion for dark matter search experiment. Improvement of sensitivity is achieved by raising density of silver halide crystals and doping well-adjusted amount of chemicals. Production of fine grained emulsion was difficult because of unexpected crystal condensation. By mixing polyvinyl alcohol (PVA) to gelatin as a binder, we succeeded in making a stable fine grained emulsion.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-04-01

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

  19. Public participation and trust in nuclear power development in China

    NARCIS (Netherlands)

    He, G.; Mol, A.P.J.; Zhang, L.; Lu, Y.

    2013-01-01

    Rapid expansion of nuclear power in China requires not only increasing institutional capacity to prevent and adequately cope with nuclear risks, but also increasing public trust in governmental agencies and nuclear enterprises managing nuclear risks. Using a case study on Haiyang nuclear power plant

  20. Public participation and trust in nuclear power development in China

    NARCIS (Netherlands)

    He, G.; Mol, A.P.J.; Zhang, L.; Lu, Y.

    2013-01-01

    Rapid expansion of nuclear power in China requires not only increasing institutional capacity to prevent and adequately cope with nuclear risks, but also increasing public trust in governmental agencies and nuclear enterprises managing nuclear risks. Using a case study on Haiyang nuclear power plant

  1. DUPIC nuclear fuel manufacturing and process technology development

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Myung Seung; Park, J. J.; Lee, J. W. [and others

    2000-05-01

    In this study, DUPIC fuel fabrication technology and the active fuel laboratory were developed for the study of spent nuclear fuel. A new nuclear fuel using highly radioactive nuclear materials can be studied at the active fuel laboratory. Detailed DUPIC fuel fabrication process flow was developed considering the manufacturing flow, quality control process and material accountability. The equipment layout of about twenty DUPIC equipment at IMEF M6 hot cell was established for the minimization of the contamination during DUPIC processes. The characteristics of the SIMFUEL powder and pellets was studied in terms of milling conditions. The characteristics of DUPIC powder and pellet was studied by using 1 kg of spent PWR fuel at PIEF nr.9405 hot cell. The results were used as reference process conditions for following DUPIC fuel fabrication at IMEF M6. Based on the reference fabrication process conditions, the main DUPIC pellet fabrication campaign has been started at IMEF M6 using 2 kg of spent PWR fuel since 2000 January. As of March 2000, about thirty DUPIC pellets were successfully fabricated.

  2. DTRA's Nuclear Explosion Monitoring Research and Development Program

    Science.gov (United States)

    Nichols, J.; Dainty, A.; Phillips, J.

    2001-05-01

    The Defense Threat Reduction Agency (DTRA) has a Program in Basic Research and Development for Nuclear Explosion Technology within the Nuclear Treaties Branch of the Arms Control Technology Division. While the funding justification is Arms Control Treaties (i.e., Comprehensive Nuclear-Test-Ban Treaty, CTBT), the results are made available for any user. Funding for the Program has averaged around \\10m per year recently. By Congressional mandate, the program has disbursed money through competitive, peer-reviewed, Program Research and Development Announcements (PRDAs); there is usually (but not always) a PRDA each year. Typical awards have been for about three years at ~\\100,000 per year, currently there are over 60 contracts in place. In addition to the "typical" awards, there was an initiative 2000 to fund seismic location calibration of the International Monitoring System (IMS) of the CTBT; there are three three-year contracts of ~\\$1,000,000 per year to perform such calibration for Eurasia, and North Africa and the Middle East. Scientifically, four technological areas have been funded, corresponding to the four technologies in the IMS: seismic, infrasound, hydroacoustic, and radionuclide, with the lion's share of the funding going to the seismic area. The scientific focus of the Program for all four technologies is detection of signals, locating their origin, and trying to determine of they are unambiguously natural in origin ("event screening"). Location has been a particular and continuing focus within the Program.

  3. Affordable Development and Qualification Strategy for Nuclear Thermal Propulsion

    Science.gov (United States)

    Gerrish, Harold P., Jr.; Doughty, Glen E.; Bhattacharyya, Samit K.

    2013-01-01

    A number of recent assessments have confirmed the results of several earlier studies that Nuclear Thermal Propulsion (NTP) is a leading technology for human exploration of Mars. It is generally acknowledged that NTP provides the best prospects for the transportation of humans to Mars in the 2030's. Its high Isp coupled with the high thrusts achievable, allow reasonable trip times, thereby alleviating concerns about space radiation and "claustrophobia" effects. NASA has embarked on the latest phase of the development of NTP systems, and is adopting an affordable approach in response to the pressure of the times. The affordable strategy is built on maximizing the use of the large NTP technology base developed in the 1950's and 60's. The fact that the NTP engines were actually demonstrated to work as planned, is a great risk reduction feature in its development. The strategy utilizes non-nuclear testing to the fullest extent possible, and uses focused nuclear tests for the essential qualification and certification tests. The perceived cost risk of conducting the ground tests is being addressed by considering novel testing approaches. This includes the use of boreholes to contain radioactive effluents, and use of fuel with very high retention capability for fission products. The use of prototype flight tests is being considered as final steps in the development prior to undertaking human flight missions. In addition to the technical issues, plans are being prepared to address the institutional and political issues that need to be considered in this major venture. While the development and deployment of NTP system is not expected to be cheap, the value of the system will be very high, and amortized over the many missions that it enables and enhances, the imputed costs will be very reasonable. Using the approach outlined, NASA and its partners, currently the DOE, and subsequently industry, have a good chance of creating a sustained development program leading to human

  4. Affordable Development and Qualification Strategy for Nuclear Thermal Propulsion

    Science.gov (United States)

    Gerrish, Harold P., Jr.; Doughty, Glen E.; Bhattacharyya, Samit K.

    2013-01-01

    Nuclear Thermal Propulsion (NTP) is a concept which uses a nuclear reactor to heat a propellant to high temperatures without combustion and can achieve significantly greater specific impulse than chemical engines. NTP has been considered many times for human and cargo missions beyond low earth orbit. A lot of development and technical maturation of NTP components took place during the Rover/NERVA program of the 60's and early 70's. Other NTP programs and studies followed attempting to further mature the NTP concept and identify a champion customer willing to devote the funds and support the development schedule to a demonstration mission. Budgetary constraints require the use of an affordable development and qualification strategy that takes into account all the previous work performed on NTP to construct an existing database, and include lessons learned and past guidelines followed. Current guidelines and standards NASA uses for human rating chemical rocket engines is referenced. The long lead items for NTP development involve the fuel elements of the reactor and ground testing the engine system, subsystem, and components. Other considerations which greatly impact the development plans includes the National Space Policy, National Environmental Policy Act, Presidential Directive/National Security Council Memorandum #25 (Scientific or Technological Experiments with Possible Large-Scale Adverse Environmental Effects and Launch of Nuclear Systems into Space), and Safeguards and Security. Ground testing will utilize non-nuclear test capabilities to help down select components and subsystems before testing in a nuclear environment to save time and cost. Existing test facilities with minor modifications will be considered to the maximum extent practical. New facilities will be designed to meet minimum requirements. Engine and test facility requirements are based on the driving mission requirements with added factors of safety for better assurance and reliability

  5. Nuclear lamins during gametogenesis, fertilization and early development

    Science.gov (United States)

    Maul, G. G.; Schatten, G.

    1986-01-01

    The distribution of lamins (described by Gerace, 1978, as major proteins of nuclear envelope) during gametogenesis, fertilization, and early development was investigated in germ cells of a mouse (Mus musculus), an echinoderm (Lytechinus variegatus), and the surf clam (Spisula solidissima) was investigated in order to determine whether the differences detected could be correlated with differences in the function of cells in these stages of the germ cells. In order to monitor the behavior of lamins, the gametes and embryos were labeled with antibodies to lamins A, C, and B extracted from autoimmune sera of patients with scleroderma and Lupus erythematosus. Results indicated that lamin B could be identified in nuclear envelopes on only those nuclei where chromatin is attached and where RNA synthesis takes place.

  6. Advanced gas cooled nuclear reactor materials evaluation and development program

    Energy Technology Data Exchange (ETDEWEB)

    1977-01-01

    Results of work performed from January 1, 1977 through March 31, 1977 on the Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program are presented. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Process Heat and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (impure Helium), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Work covered in this report includes progress to date on alloy selection for VHTR Nuclear Process Heat (NPH) applications and for DCHT applications. The present status on the simulated reactor helium loop design and on designs for the testing and analysis facilities and equipment is discussed.

  7. Development of dry storage technology of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Maruoka, Kunio [Mitsubishi Heavy Industries Ltd., Yokohama (Japan). Nuclear Energy Systems Engineering Center; Murakami, Kazuo; Yokoyama, Takeshi; Natsume, Tomohiro; Irino, Mitsuhiro

    1998-07-01

    The increasing demand for storage of spent fuel assemblies generated by commercial nuclear power plants is the urgent subject to solve. The dry storage system is as economically more advantageous than the pool storage system, and so, Mitsubishi Heavy Industries, Ltd. has developed the metal storage cask suited to small and medium storage capacity under 2000MTU - 3000MTU. For large scale capacity, the new `Mitsubishi Vault Storage System` has been developed, and it provides a safe and economical solution. Technical study concerning cooling ability was performed. (author)

  8. Developments and needs in nuclear analysis of fusion technology

    Energy Technology Data Exchange (ETDEWEB)

    Pampin, R., E-mail: raul.pampin@f4e.europa.eu [CCFE, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Davis, A. [CCFE, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Izquierdo, J. [F4E Fusion For Energy, Josep Pla 2, Torres Diagonal Litoral B3, Barcelona 08019 (Spain); Leichtle, D. [Karlsruhe Institute of Technology (KIT), Hermann-von-Helmholtz Platz 1, D-76344 Karlsruhe (Germany); Loughlin, M.J. [ITER Organisation, Route de Vinon sur Verdon, 13115 Saint Paul lez Durance (France); Sanz, J. [UNED, Departamento de Ingenieria Energetica, Juan del Rosal 12, 28040 Madrid (Spain); Turner, A. [CCFE, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Villari, R. [Associazione EURATOM-ENEA sulla Fusione, Via Enrico Fermi 45, 00044 Frascati, Rome (Italy); Wilson, P.P.H. [University of Wisconsin, Nuclear Engineering Department, Madison, WI (United States)

    2013-10-15

    Highlights: • Complex fusion nuclear analyses require detailed models, sophisticated acceleration and coupling of cumbersome tools. • Progress on development of tools and methods to meet specific needs of fusion nuclear analysis reported. • Advances in production of reference models and in preparation and QA of acceleration and coupling algorithms shown. • Evaluation and adaptation studies of alternative transport codes presented. • Discussion made of the importance of efforts in these and other areas, considering some of the more pressing needs. -- Abstract: Nuclear analyses provide essential input to the conceptual design, optimisation, engineering and safety case of fusion technology in current experiments, ITER, next-step devices and power plant studies. Calculations are intricate and computer-intensive, typically requiring detailed geometry models, sophisticated acceleration algorithms, high-performance parallel computations, and coupling of large and complex transport and activation codes and databases. This paper reports progress on some key areas in the development of tools and methods to meet the specific needs of fusion nuclear analyses. In particular, advances in the production and modernisation of reference models, in the preparation and quality assurance of acceleration algorithms and coupling schemes, and in the evaluation and adaptation of alternative transport codes are presented. Emphasis is given to ITER-relevant activities, which are the main driver of advances in the field. Discussion is made of the importance of efforts in these and other areas, considering some of the more pressing needs and requirements. In some cases, they call for a more efficient and coordinated use of the scarce resources available.

  9. Evolutionary developments of advanced PWR nuclear fuels and cladding materials

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kyu-Tae, E-mail: ktkim@dongguk.ac.kr

    2013-10-15

    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{sup −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.

  10. New nuclear technology; International developments. Review 1995; Ny kaernteknik; Utvecklingsinsatser internationellt. Sammanfattning och oeversikt 1995

    Energy Technology Data Exchange (ETDEWEB)

    Devell, L.; Aggeryd, I.; Hultgren, Aa.; Lundell, B.; Pedersen, T.

    1995-09-01

    A summary review of the development of new nuclear rector technology is presented in this report. Fuel cycle strategies and waste handling developments are also commented. Different plans for dismantling nuclear weapons are presented. 18 refs.

  11. Obstacles to the nuclear technology development in Brazil: from the beginning of atomic age to the Brazil-Germany Nuclear Agreement; Entraves ao desenvolvimento da tecnologia nuclear no Brasil: dos primordios da era atomica ao Acordo Nuclear Brasil-Alemanha

    Energy Technology Data Exchange (ETDEWEB)

    Medeiros, Tharsila Reis de

    2005-07-01

    This paper intends to comprehend the Brazilian social actors' efforts applied to the nuclear energy control, from the beginning of Atomic Age to Brazil-Germany Nuclear Agreement. It tries to demonstrate that the limits of The Brazilian nuclear development in this period derive from the capitalist development dynamics in Brazil and from the absence of continuity on the motivations of its nuclear policy. (author)

  12. Development of a research nuclear reactor simulator using LABVIEW®

    Energy Technology Data Exchange (ETDEWEB)

    Lage, Aldo Marcio Fonseca; Mesquita, Amir Zacarias; Pinto, Antonio Juscelino; Souza, Luiz Claudio Andrade [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2015-07-01

    The International Atomic Energy Agency recommends the use of safety and friendly interfaces for monitoring and controlling the operational parameters of the nuclear reactors. The most important variable in the nuclear reactors control is the power released by fission of the fuel in the core which is directly proportional to neutron flux. It was developed a digital system to simulate the neutron evolution flux and monitoring their interaction on the other operational parameters. The control objective is to bring the reactor power from its source level (mW) to a few W. It is intended for education of basic reactor neutronic principles such as the multiplication factor, criticality, reactivity, period, delayed neutron and control by rods. The 250 kW IPR-R1 TRIGA research reactor at Nuclear Technology Development Center - CDTN (Belo Horizonte/Brazil) was used as reference. TRIGA reactors, developed by General Atomics (GA), are the most widely used research reactor in the world. They are cooled by light water under natural convection and are characterized by being inherently safety. The simulation system was developed using the LabVIEW® (Laboratory Virtual Instruments Engineering Workbench) software, considering the modern concept of virtual instruments (VI's). The main purpose of the system is to provide to analyze the behavior, and the tendency of some processes that occur in the reactor using a user-friendly operator interface. The TRIGA simulator system will allow the study of parameters, which affect the reactor operation, without the necessity of using the facility.(author)

  13. Current state of nuclear fuel cycles in nuclear engineering and trends in their development according to the environmental safety requirements

    Science.gov (United States)

    Vislov, I. S.; Pischulin, V. P.; Kladiev, S. N.; Slobodyan, S. M.

    2016-08-01

    The state and trends in the development of nuclear fuel cycles in nuclear engineering, taking into account the ecological aspects of using nuclear power plants, are considered. An analysis of advantages and disadvantages of nuclear engineering, compared with thermal engineering based on organic fuel types, was carried out. Spent nuclear fuel (SNF) reprocessing is an important task in the nuclear industry, since fuel unloaded from modern reactors of any type contains a large amount of radioactive elements that are harmful to the environment. On the other hand, the newly generated isotopes of uranium and plutonium should be reused to fabricate new nuclear fuel. The spent nuclear fuel also includes other types of fission products. Conditions for SNF handling are determined by ecological and economic factors. When choosing a certain handling method, one should assess these factors at all stages of its implementation. There are two main methods of SNF handling: open nuclear fuel cycle, with spent nuclear fuel assemblies (NFAs) that are held in storage facilities with their consequent disposal, and closed nuclear fuel cycle, with separation of uranium and plutonium, their purification from fission products, and use for producing new fuel batches. The development of effective closed fuel cycles using mixed uranium-plutonium fuel can provide a successful development of the nuclear industry only under the conditions of implementation of novel effective technological treatment processes that meet strict requirements of environmental safety and reliability of process equipment being applied. The diversity of technological processes is determined by different types of NFA devices and construction materials being used, as well as by the composition that depends on nuclear fuel components and operational conditions for assemblies in the nuclear power reactor. This work provides an overview of technological processes of SNF treatment and methods of handling of nuclear fuel

  14. Advanced nuclear materials development -Development of superconductor application technology-

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Kye Won; Lee, Heui Kyoon; Lee, Hoh Jin; Kim, Chan Joong; Jang, Kun Ik; Kim, Kee Baek; Kwon, Sun Chil; Park, Hae Woong; Yoo, Jae Keun; Kim, Jong Jin; Jang, Joong Chul; Yang, Suk Woo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    Fabrication of high Tc bulk superconductor and its application, fabrication of superconducting wire for electric power device and analysis for cryogenic system were carried out for developing superconductor application technologies for electric power system. High quality YBaCuO bulk superconductor was fabricated by controlling initial powder preparation process and prototype fly wheel energy storage device was designed basically. The superconducting levitation force measuring device was made to examine the property of prepared superconductor specimen. Systematic studies on the method of starting powder preparation, mechanical fabrication process, heat treatment condition and analysis of plastic deformation were carried out to increase the stability and reproducibility of superconducting wire. A starting powder with good reactivity and fine particle size was obtained by emulsion drying method. Ag/BSCCO tape with good cross sectional shape and Tc of 16,000 A/cm{sup 2} was fabricated by applying CIP packing procedure. Multifilamentary wire with the Jc of approx. 10000 A/cm{sup 2} was fabricated by rolling method using square billet as starting shape. The joining of the multifilament wire was done by etching and pressing process and showed 50% of joining efficiency. Analysis on the heat loss in cryostat for high Tc superconducting device was carried out for optimum design of the future cryogenic system. 126 figs, 14 tabs, 214 refs. (Author).

  15. Nuclear Power for Sustainable Development : Current Status and Future Prospects

    OpenAIRE

    Adamantiades, A.; Kessides, I.

    2009-01-01

    Interest in nuclear power has been revived as a result of volatile fossil fuel prices, concerns about the security of energy supplies, and global climate change. This paper describes the current status and future plans for expansion of nuclear power, the advances in nuclear reactor technology, and their impacts on the associated risks and performance of nuclear power. Advanced nuclear reactors have been designed to be simpler and safer, and to have lower costs than currently operating reactor...

  16. Nuclear material surveillance system for DUPIC fuel development facility

    Energy Technology Data Exchange (ETDEWEB)

    Song, D. Y.; Lee, S. Y.; Ha, J. H.; Go, W. I.; Kim, H. D. [KAERI, Taejon (Korea, Republic of)

    2004-07-01

    Unattended continuous surveillance systems for safeguards of nuclear facility result in large amounts of image and radiation data, which require much time and effort to inspect. Therefore, it is necessary to develop system that automatically pinpoints and diagnoses the anomalies from data. In this regards, this paper presents a novel concept of the continuous surveillance system that integrates visual image and radiation data by the use of neural networks based on self-organized feature mapping. This surveillance system is stably operating for safeguards of the DUPIC (DFDF) in KAERI.

  17. Development of RCM analysis software for Korean nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Ho; Choi, Kwang Hee; Jeong, Hyeong Jong [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1998-12-31

    A software called KEPCO RCM workstation (KRCM) has been developed to optimize the maintenance strategies of Korean nuclear power plants. The program modules of the KRCM were designed in a manner that combines EPRI methodologies and KEPRI analysis technique. The KRCM is being applied to the three pilot system, chemical and volume control system, main steam system, and compressed air system of Yonggwang Units 1 and 2. In addition, the KRCM can be utilized as a tool to meet a part of the requirements of maintenance rule (MR) imposed by U.S. NRC. 3 refs., 4 figs. (Author)

  18. The Nuclear Security Summit and Saft Development of China’s Nuclear Energy

    Institute of Scientific and Technical Information of China (English)

    Xu; Yu

    2014-01-01

    China always attaches great importance to the issue of nuclear safety,is opposed to nuclear terrorism,actively supports the strengthening of international cooperation,and has made remarkable achievements by actively participating in and promoting international nuclear security activities,

  19. Wdr68 requires nuclear access for craniofacial development.

    Directory of Open Access Journals (Sweden)

    Bingyan Wang

    Full Text Available Wdr68 is a highly conserved scaffolding protein required for craniofacial development and left-right asymmetry. A Ras-Map3k-Wdr68-Dyrk1 signaling relay may mediate these and other diverse signaling events important in development and disease. While the sub-cellular localization of Wdr68 has been shown to be dependent on that of its interaction partners, it is not clear where Wdr68 activity is required during development. Here we show that while a GFP-Wdr68 fusion functionally substituted for craniofacial development in the zebrafish, that a Nuclear Export Signal (NES fusion protein (GFPNESWdr68 failed to support craniofacial development. As control for NES activity, we show that while GFP-Wdr68 exhibited a pan-cellular distribution in C2C12 cells, the GFPNESWdr68 fusion predominantly localized to the cell cytoplasm, as expected. Interestingly, while GFP-Wdr68 and RFP-Dyrk1a co-localized to the cell nucleus as expected based on the known sub-cellular localization for Dyrk1a, we found that the GFPNESWdr68 fusion redistributed RFP-Dyrk1a to the cell cytoplasm potentially disconnecting the Ras/Dyrk1 signal relay from further downstream targets. Consistent with a nuclear role in gene regulation, we also found that while a transcriptional activation domain fusion, CebpFlagWdr68, functionally substituted for endogenous Wdr68 for craniofacial development, that a transcriptional repression domain fusion, MadFlagWdr68, failed to support craniofacial development. Dyrk1b is required for myogenin (myog expression in differentiating mouse C2C12 cells and here we report that wdr68 is also important for myog expression in differentiating C2C12 cells. Using a C2C12 cell myog promoter-reporter system, we found that Wdr68 overexpression increased reporter activity while moderate expression levels of MadFlagWdr68 interfered with reporter activity. Taken together, these findings support a nuclear role for Wdr68-containing complexes.

  20. The right and development: the nuclear right; O direito e o desenvolvimento: o direito nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Coimbra, Guilhermina Lavos

    1986-02-01

    The author analyses some juridical instruments signed among Brazil and his commercial partners in the nuclear field: the way as it has been reflected and it has modeled the Brazilian Nuclear Program - BNP. It is very much important a Nuclear Law/Bill of the Nuclear Rights directed to the uranium and the BNP defense. It is compared the Brazilian petroleum situation, before 1952, with the present uranium situation. It is purposed a Constitutional disposal, protecting the uranium and all the other nuclear strategic minerals state monopoly, to be inserted in the next Brazilian Constitution and the URANIOBRAS creation, similar to PETROBRAS. (author). 163 refs.

  1. Engine System Model Development for Nuclear Thermal Propulsion

    Science.gov (United States)

    Nelson, Karl W.; Simpson, Steven P.

    2006-01-01

    In order to design, analyze, and evaluate conceptual Nuclear Thermal Propulsion (NTP) engine systems, an improved NTP design and analysis tool has been developed. The NTP tool utilizes the Rocket Engine Transient Simulation (ROCETS) system tool and many of the routines from the Enabler reactor model found in Nuclear Engine System Simulation (NESS). Improved non-nuclear component models and an external shield model were added to the tool. With the addition of a nearly complete system reliability model, the tool will provide performance, sizing, and reliability data for NERVA-Derived NTP engine systems. A new detailed reactor model is also being developed and will replace Enabler. The new model will allow more flexibility in reactor geometry and include detailed thermal hydraulics and neutronics models. A description of the reactor, component, and reliability models is provided. Another key feature of the modeling process is the use of comprehensive spreadsheets for each engine case. The spreadsheets include individual worksheets for each subsystem with data, plots, and scaled figures, making the output very useful to each engineering discipline. Sample performance and sizing results with the Enabler reactor model are provided including sensitivities. Before selecting an engine design, all figures of merit must be considered including the overall impacts on the vehicle and mission. Evaluations based on key figures of merit of these results and results with the new reactor model will be performed. The impacts of clustering and external shielding will also be addressed. Over time, the reactor model will be upgraded to design and analyze other NTP concepts with CERMET and carbide fuel cores.

  2. Technology development for nuclear power generation for space application

    Energy Technology Data Exchange (ETDEWEB)

    Guimaraes, Lamartine N.F.; Ribeiro, Guilherme B.; Braz Filho, Francisco A.; Nascimento, Jamil A.; Placco, Guilherme M., E-mail: guimarae@ieav.cta.br, E-mail: lamartine.guimaraes@pq.cnpq.br [Instituto de Estudos Avancados (IEAv), Sao Jose dos Campos, SP (Brazil). Divisao de Energia Nuclear; Faria, Saulo M. de [Instituto Tecnologico de Aeronautica (ITA), Sao Jose dos Campos, SP (Brazil)

    2015-07-01

    For a few years now, the TERRA project is developing several technology pieces to foster nuclear space applications. In this way, a nuclear reactor concept has been developed as a first proposal. Together, the problem of heat to electricity conversion has been addressed. A closed Brayton cycle is being built and a Stirling machine is being worked out and perfected. In addition, two types of heat pipes are being look at. One related with high temperature made of Mo13Re, an especial alloy. And a second one made of copper, which mainly could be used as a passive heat rejection. In this way, all major areas of interest in a micro station to be used in space has been addressed. A new passive technology has been inferred and is related with Tesla turbine or its evolution, known as multi fluid passive turbine. This technology has the potential to either: improve the Brayton cycle or its efficiency. In this paper, some details are discussed and some will be shown during the presentation, as the work evolve. (author)

  3. A study on the development and application of expert system for nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Hee Gon; Kim, Seong Bok [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

    1995-12-31

    It is a final report of the research that is a study on the development and application of expert system for nuclear power plants and development of the schemes computing environments and user interfaces for the expert system, which is a systematic and efficient development of expert system for nuclear power plants in the future. This report is consisted of -Development trends of expert system for nuclear power plants. -Classification of expert system applications for nuclear power plants. -Systematic and efficient developments schemes of expert system for nuclear power plants, and -Suitable computing environments and user interfaces for the expert systems. (author). 113 refs., 85 figs.

  4. Development of the nuclear plant analyzer for Korean standard Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Shin Hwan; Kim, Hyeong Heon; Song, In Ho; Hong, Eon Yeong; Oh, Yeong Taek [Korea Power Engineering Company Inc., Yongin (Korea, Republic of)

    2000-12-15

    The purpose of this study is to develop an NPA for the Ulchin Nuclear Power Plant Unit 3 and 4, the first KSNP type plant. In this study, the process model simulating the overall plant systems, GUI and simulation executive which provide the functions of an engineering simulator were developed, and the NPA was completed by integrating them. The contents and the scope of this study are as follows : main feedwater system, auxiliary feedwater system, Chemical and Volume Control System(CVCS), Safety Injection System(SIS), Shutdown Cooling System(SCS), electric power supply system, Core Protection Calculator(CPC), various plant control system, development of the graphics screens for each system, real-time simulation, simulation control for the enhancement of functional capabilities, user friendly GUI, collection of the design and operating data, establishment of the NPA database, integration of the GUI and simulation control program with process model, collection of the data for the verification and validation of the developed NPA, collection of the plant test data, collection and review of the results of other computer codes, verification of the simulation accuracy by comparing the NPA results with the actual plant data, validation of the simulation capability of the NPA, comparison against available data from other analysis suing different computer codes.

  5. Big ambitions, small returns: Nuclear energy development in China and India

    Energy Technology Data Exchange (ETDEWEB)

    Xu, Yi-hong

    2010-09-15

    This paper examines nuclear energy development in China and India and the obstacles they face. It discusses the challenges for nuclear expansion: technology, economic, nuclear fuel, and public acceptance. It concludes that (1) on all three counts - energy demands, energy security and environmental pollution - the potential impact of nuclear energy will be minimal in both countries; and (2) despite the political, financial and technical obstacles for nuclear expansion and the minimal contribution of energy security, both countries will devote financial, human and political resources to their nuclear expansion. Its speed will depend on domestic and international political development.

  6. Development of a Vehicle Special Nuclear Material Monitors

    Institute of Scientific and Technical Information of China (English)

    ZHAORong-sheng

    2003-01-01

    Vehicle special nuclear material (SNM) monitors are mainly used at the portals of nuclear facilities to verify the vehicles going out from the facilities for preventing from unauthorized SNM transfer.

  7. DUPIC nuclear fuel manufacturing and process technology development at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Yim, Sung Paal; Lee, Jung Won; Kim, Jong Ho; Kim, Soo Sung; Kim, Woong Ki; Yang, Myung Seung [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2000-07-01

    DUPIC fuel cycle development project in KAERI of Korea was initiated in 1991 and has advanced in relevant technologies for last 10 years. The project includes five different topics such as nuclear fuel manufacturing, compatibility evaluation, performance evaluation, manufacturing facility management, and safeguards. The contents and results of DUPIC R and D up to now are as follow: - the basic foundation was established for the critically required pelletizing technology and powder treatment technology for DUPIC. - development of DUPIC process line and deployment of 20 each process equipment and examination instruments in DFDF. - powder and pellet characterization study was done at PIEF based on the simfuel study results, and 30 DUPIC pellets were successfully produced. - the manufactured pellets were used for sample fuel rods irradiated in July,2000 in HANARO research reactor in KAERI and has been under post irradiation examination. (Hong, J. S.)

  8. Development of an educational nuclear research reactor simulator

    Energy Technology Data Exchange (ETDEWEB)

    Arafa, Amany Abdel Aziz; Saleh, Hassan Ibrahim [Atomic Energy Authority, Cairo (Egypt). Radiation Engineering Dept.; Ashoub, Nagieb [Atomic Energy Authority, Cairo (Egypt). Reactor Physics Dept.

    2014-12-15

    This paper introduces the development of a research reactor educational simulator based on LabVIEW that allows the training of operators and studying different accident scenarios and the effects of operational parameters on the reactor behavior. Using this simulator, the trainee can test the interaction between the input parameters and the reactor activities. The LabVIEW acts as an engine implements the reactor mathematical models. In addition, it is used as a tool for implementing the animated graphical user interface. This simulator provides the training requirements for both of the reactor staff and the nuclear engineering students. Therefore, it uses dynamic animation to enhance learning and interest for a trainee on real system problems and provides better visual effects, improved communications, and higher interest levels. The benefits of conducting such projects are to develop the expertise in this field and save costs of both operators training and simulation courses.

  9. Development of Computer-Aided Learning Programs on Nuclear Nonproliferation and Control

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyun Chul [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2011-10-15

    The fulfillment of international norms for nuclear nonproliferation is indispensable to the promotion of nuclear energy. The education and training for personnel and mangers related to the nuclear material are one of crucial factors to avoid unintended non-compliance to international norms. Korea Institute of Nuclear Nonproliferation and Control (KINAC) has been providing education and training on nuclear control as its legal duty. One of the legally mandatory educations is 'nuclear control education' performed since 2006 for the observation of the international norms on nuclear nonproliferation and the spread of the nuclear control culture. The other is 'physical protection education' performed since 2010 for maintaining the national physical protection regime effectively and the spread of the nuclear security culture. The 2010 Nuclear Security Summit was held in Washington, DC to enhance international cooperation to prevent nuclear terrorism. During the Summit, the South Korea was chosen to host the second Nuclear Summit in 2012. South Korean President announced that South Korea would share its expertise and support the Summit's mission by setting up an international education and training center on nuclear security in 2014. KINAC is making a full effort to set up the center successfully. An important function of the center is education and training in the subjects of nuclear nonproliferation, nuclear safeguards, nuclear security, and nuclear export/import control. With increasing importance of education and training education on nuclear nonproliferation and control, KINAC has been developing computer-aided learning programs on nuclear nonproliferation and control to overcome the weaknesses in classroom educations. This paper shows two learning programs. One is an e-learning system on the nuclear nonproliferation and control and the other is a virtual reality program for training nuclear material accountancy inspection of light water

  10. Nuclear localization of Annexin A7 during murine brain development

    Directory of Open Access Journals (Sweden)

    Noegel Angelika A

    2005-04-01

    Full Text Available Abstract Background Annexin A7 is a member of the annexin protein family, which is characterized by its ability to interact with phospholipids in the presence of Ca2+-ions and which is thought to function in Ca2+-homeostasis. Results from mutant mice showed altered Ca2+-wave propagation in astrocytes. As the appearance and distribution of Annexin A7 during brain development has not been investigated so far, we focused on the distribution of Annexin A7 protein during mouse embryogenesis in the developing central nervous system and in the adult mouse brain. Results Annexin A7 is expressed in cells of the developing brain where a change in its subcellular localization from cytoplasm to nucleus was observed. In the adult CNS, the subcellular distribution of Annexin A7 depends on the cell type. By immunohistochemistry analysis Annexin A7 was detected in the cytosol of undifferentiated cells at embryonic days E5–E8. At E11–E15 the protein is still present in the cytosol of cells predominantly located in the ventricular germinative zone surrounding the lateral ventricle. Later on, at embryonic day E16, Annexin A7 in cells of the intermediate and marginal zone of the neopallium translocates to the nucleus. Neuronal cells of all areas in the adult brain present Annexin A7 in the nucleus, whereas glial fibrillary acidic protein (GFAP-positive astrocytes exhibit both, a cytoplasmic and nuclear staining. The presence of nuclear Annexin A7 was confirmed by extraction of the nucleoplasm from isolated nuclei obtained from neuronal and astroglial cell lines. Conclusion We have demonstrated a translocation of Annexin A7 to nuclei of cells in early murine brain development and the presence of Annexin A7 in nuclei of neuronal cells in the adult animal. The role of Annexin A7 in nuclei of differentiating and mature neuronal cells remains elusive.

  11. Next Generation Nuclear Plant Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    None

    2005-01-01

    The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: (1) Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission (2) Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: (1) High temperature gas reactor fuels behavior; (2) High temperature materials qualification; (3) Design methods development and validation; (4) Hydrogen production technologies; and (5) Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented

  12. Comprehensive Nuclear-Test-Ban Treaty: Background and Current Developments

    Science.gov (United States)

    2013-01-02

    Offer Tools for Nuclear Testing—and Solving Nuclear Mysteries ,” Washington Post, November 1, 2011, p. 1. Horovitz, Liviu, “A Detour Strategy for the...Today, October 2009, pp. 46-52. Kimball, Daryl, “Reconsidering the Nuclear Test Ban Treaty: Sorting Fact from Fiction ,” Arms Control Association

  13. Development of Modeling Approaches for Nuclear Thermal Propulsion Test Facilities

    Science.gov (United States)

    Jones, Daniel R.; Allgood, Daniel C.; Nguyen, Ke

    2014-01-01

    High efficiency of rocket propul-sion systems is essential for humanity to venture be-yond the moon. Nuclear Thermal Propulsion (NTP) is a promising alternative to conventional chemical rock-ets with relatively high thrust and twice the efficiency of the Space Shuttle Main Engine. NASA is in the pro-cess of developing a new NTP engine, and is evaluat-ing ground test facility concepts that allow for the thor-ough testing of NTP devices. NTP engine exhaust, hot gaseous hydrogen, is nominally expected to be free of radioactive byproducts from the nuclear reactor; how-ever, it has the potential to be contaminated due to off-nominal engine reactor performance. Several options are being investigated to mitigate this hazard potential with one option in particular that completely contains the engine exhaust during engine test operations. The exhaust products are subsequently disposed of between engine tests. For this concept (see Figure 1), oxygen is injected into the high-temperature hydrogen exhaust that reacts to produce steam, excess oxygen and any trace amounts of radioactive noble gases released by off-nominal NTP engine reactor performance. Water is injected to condense the potentially contaminated steam into water. This water and the gaseous oxygen (GO2) are subsequently passed to a containment area where the water and GO2 are separated into separate containment tanks.

  14. Next Generation Nuclear Plant Materials Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    G.O. Hayner; R.L. Bratton; R.N. Wright

    2005-09-01

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R&D Program includes the following elements: (1) Developing a specific approach, program plan and other project management tools for

  15. Co-operation Agreement between the Ministry of Science, Technology and Environment of the Republic of Cuba (CITMA) and CERN concerning The Further Development of Scientific and Technical Co-operation

    CERN Document Server

    2003-01-01

    In the framework of the CERN collaboration with Latin America, co-operation agreements have been established with Argentina, Brazil, Colombia, Chile, Mexico and Peru. They have made possible a growing participation by Latin American particle physicists in the CERN programme, which has important potential for the future. The Cuban particle physics community is highly motivated and relatively advanced, both scientifically and technologically, since many of its members have been trained in installations of the former Soviet Union, many of which now participate in CERN's cooperation with Russia. In addition, Cuba has a good number of experienced computer scientists. A group from the Cuban Institute CEADEN (Centro de Aplicaciones Tecnológicas y Desarollo Nuclear) has recently been accepted unanimously into the ALICE collaboration, with agreed contributions to off-line software and Grid middlewave. Additional Cuban contributions to show controls, data acquisition and testing electronics for the Silicon drift decte...

  16. Development of Core Monitoring System for Nuclear Power Plants (I)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, S.H.; Kim, Y.B.; Park, M.G; Lee, E.K.; Shin, H.C.; Lee, D.J. [Korea Electric Power Research Institute, Daejeon (Korea, Republic of)

    1997-12-31

    1.Object and Necessity of the Study -The main objectives of this study are (1)conversion of APOLLO version BEACON system to HP-UX version core monitoring system, (2)provision of the technical bases to enhance the in-house capability of developing more advanced core monitoring system. 2.Results of the Study - In this study, the revolutionary core monitoring technologies such as; nodal analysis and isotope depletion calculation method, advanced schemes for power distribution control, and treatment of nuclear databank were established. The verification and validation work has been successfully performed by comparing the results with those of the design code and measurement data. The advanced graphic user interface and plant interface method have been implemented to ensure the future upgrade capability. The Unix shell scripts and system dependent software are also improved to support administrative functions of the system. (author). 14 refs., 112 figs., 52 tabs.

  17. Present and future radioactive nuclear beam developments at Argonne

    Energy Technology Data Exchange (ETDEWEB)

    Decrock, P.

    1996-11-01

    A scheme for building an ISOL-based radioactive nuclear beam facility at the Argonne Physics Division, is currently evaluated. The feasibility and efficiency of the different steps in the proposed production- and acceleration cycles are being tested. At the Dynamitron Facility of the ANL Physics Division, stripping yields of Kr, Xe and Ph beams in a windowless gas cell have been measured and the study of fission of {sup 238}U induced by fast neutrons from the {sup 9}Be(dn) reaction is in progress. Different aspects of the post-acceleration procedure are currently being investigated. In parallel with this work, energetic radioactive beams such as {sup 17}F, {sup 18}F and {sup 56}Ni have recently been developed at Argonne using the present ATLAS facility.

  18. Development of thyroid anthropomorphic phantoms for use in nuclear medicine

    Science.gov (United States)

    Cerqueira, R. A. D.; Maia, A. F.

    2014-02-01

    The objective of this study was to develop thyroid anthropomorphic phantoms to be used in control tests of medical images in scintillation cameras. The main difference among the phantoms was the neck shape: in the first, called OSCT, it was geometrically shaped, while in the second, called OSAP, it was anthropomorphically shaped. In both phantoms, thyroid gland prototypes, which were made of acrylic and anthropomorphically shaped, were constructed to allow the simulation of a healthy thyroid and of thyroids with hyperthyroidism and hypothyroidism. Images of these thyroid anthropomorphic phantoms were obtained using iodine 131 with an activity of 8.695 MBq. The iodine 131 was chosen because it is widely used in studies of thyroid scintigraphy. The images obtained proved the effectiveness of the phantoms to simulate normal or abnormal thyroids function. These phantoms can be used in medical imaging quality control programs and, also in the training of professionals involved in the analysis of images in nuclear medicine centers.

  19. The supervisions in the field develop nuclear professionals; Las supervisiones en campo desarrollan profesionales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez de la Casa, M.; Buedo, J. L.; Gonzalez, F.

    2015-07-01

    In 2011 Cofrentes Nuclear Power Plants began a training program for improving the supervision of managers in the field: the effort done not only has improved the quality of supervisions but also has defined a way to reinforce behavior expectations of Cofrentes Nuclear Power Plant. (Author)

  20. Development of Metallic Magnetic Calorimeters for Nuclear Safeguards Applications

    Energy Technology Data Exchange (ETDEWEB)

    Bates, Cameron Russell [Univ. of California, Berkeley, CA (United States)

    2015-03-11

    Many nuclear safeguards applications could benefit from high-resolution gamma-ray spectroscopy achievable with metallic magnetic calorimeters. This dissertation covers the development of a system for these applications based on gamma-ray detectors developed at the University of Heidelberg. It demonstrates new calorimeters of this type, which achieved an energy resolution of 45.5 eV full-width at half-maximum at 59.54 keV, roughly ten times better than current state of the art high purity germanium detectors. This is the best energy resolution achieved with a gamma-ray metallic magnetic calorimeter at this energy to date. In addition to demonstrating a new benchmark in energy resolution, an experimental system for measuring samples with metallic magnetic calorimeters was constructed at Lawrence Livermore National Laboratory. This system achieved an energy resolution of 91.3 eV full-width at half-maximum at 59.54 keV under optimal conditions. Using this system it was possible to characterize the linearity of the response, the count-rate limitations, and the energy resolution as a function of temperature of the new calorimeter. With this characterization it was determined that it would be feasible to measure 242Pu in a mixed isotope plutonium sample. A measurement of a mixed isotope plutonium sample was performed over the course of 12 days with a single two-pixel metallic magnetic calorimeter. The relative concentration of 242Pu in comparison to other plutonium isotopes was determined by direct measurement to less than half a percent accuracy. This is comparable with the accuracy of the best-case scenario using traditional indirect methods. The ability to directly measure the relative concentration of 242Pu in a sample could enable more accurate accounting and detection of indications of undeclared activities in nuclear safeguards, a better constraint on source material in forensic samples containing plutonium, and improvements in verification in a future plutonium

  1. Development of life evaluation technology for nuclear power plant components

    Energy Technology Data Exchange (ETDEWEB)

    Song, Sung Jin; Kim, Young Hwan; Shin, Hyun Jae [Sungkwunkwan Univ., Seoul (Korea, Republic of); Lee, Hyang Beom [Soongsil Univ., Seoul (Korea, Republic of); Shin, Young Kil [Kunsan National Univ., Gunsan (Korea, Republic of); Chung, Hyun Jo [Wonkwang Univ., Iksan (Korea, Republic of); Park, Ik Keun; Park, Eun Soo [Seoul National University of Technology, Seoul (Korea, Republic of)

    2001-03-15

    Retaining reliabilities of nondestructive testing is essential for the life-time maintenance of nuclear power plant. In order to Improve reliabilities of ultrasonic testing and eddy current testing, the following five subjects were carried out in this study: development of BEM analysis technique for ECT of SG tube, development of neural network technique for the intelligent analysis of ECT flaw signals of SG tubes, development of RFECT technology for the inspection of SG tube, FEM analysis of ultrasonic scattering field and evaluation of statistical reliability of PD-RR test of ultrasonic testing. As results, BEM analysis of eddy current signal, intelligent analysis of eddy current signal using neural network, and FEM analysis of remote field eddy current testing have been developed for the inspection of SG tubes. FEM analysis of ultrasonic waves in 2-dimensional media and evaluation of statistical reliability of ultrasonic testing with PD-RR test also have been carried out for the inspection of weldments. Those results can be used to Improve reliability of nondestructive testing.

  2. The Activities of the European Consortium on Nuclear Data Development and Analysis for Fusion

    Energy Technology Data Exchange (ETDEWEB)

    Fischer, U., E-mail: ulrich.fischer@kit.edu [Karlsruhe Institute of Technology, Institute for Neutron Physic and Reactor Technology, 76344 Eggenstein-Leopoldshafen (Germany); Avrigeanu, M.; Avrigeanu, V. [Horia Hulubei National Institute of Physics and Nuclear Engineering (IFIN-HH), RO-077125 Magurele (Romania); Cabellos, O. [Departamento de Ingenieria Nuclear, Universidad Politecnica de Madrid, 28006 Madrid (Spain); Kodeli, I. [Jozef Stefan Institute (JSI), Jamova 39, 1000 Ljubljana (Slovenia); Koning, A. [Nuclear Research and Consultancy Group (NRG), Westerduinweg 3, 1755 LE Petten (Netherlands); Konobeyev, A.Yu. [Karlsruhe Institute of Technology, Institute for Neutron Physic and Reactor Technology, 76344 Eggenstein-Leopoldshafen (Germany); Leeb, H. [Technische Universitaet Wien, Atominstitut, Wiedner Hauptstrasse 8–10, 1040 Wien (Austria); Rochman, D. [Nuclear Research and Consultancy Group (NRG), Westerduinweg 3, 1755 LE Petten (Netherlands); Pereslavtsev, P. [Karlsruhe Institute of Technology, Institute for Neutron Physic and Reactor Technology, 76344 Eggenstein-Leopoldshafen (Germany); Sauvan, P. [Universidad Nacional de Educacion a Distancia, C. Juan del Rosal, 12, 28040 Madrid (Spain); Sublet, J.-C. [Euratom/CCFE Fusion Association, Culham Science Centre, OX14 3DB (United Kingdom); Trkov, A. [Jozef Stefan Institute (JSI), Jamova 39, 1000 Ljubljana (Slovenia); Dupont, E. [OECD Nuclear Energy Agency, Paris (France); Leichtle, D.; Izquierdo, J. [Fusion for Energy, Barcelona (Spain)

    2014-06-15

    This paper presents an overview of the activities of the European Consortium on Nuclear Data Development and Analysis for Fusion. The Consortium combines available European expertise to provide services for the generation, maintenance, and validation of nuclear data evaluations and data files relevant for ITER, IFMIF and DEMO, as well as codes and software tools required for related nuclear calculations.

  3. Evaluation of nuclear data for R and D projects; development of database for medical nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Tae Suk [Catholic University, Seoul (Korea); Shin, D. O. [Kyung Hee University, Seoul (Korea); Joh, C. W.; Chang, J. S. [Ajou University, Suwon (Korea); Choi, Y. [Sungkyunkwan University, Seoul (Korea); Kim, S. H. [Hanyang University, Seoul (Korea); Park, S. Y. [National Cancer Center, Seoul (Korea); Shin, D. H.; Lee, S [Kyonggi University, Seoul (Korea)

    2002-04-01

    Medical nuclear data used in the country is not provided by academic associations and organizations concerned and even by government organizations concerned. This is aimed to investigate the diagnostic and therapeutic equipments in the clinical use and the domestic present status of nuclear data and physical properties of sealed or unsealed radioactive isotopes and to establish the nuclear database. About 120 domestic centers take nuclear medicine tests and 52 medical centers do radiotherapy. The 30-odd different kinds of radionuclides are usually used in nuclear medicine in the country. The 30-odd kinds of unsealed sources are used for diagnosis and therapy and 10-odd kinds of sealed sources for brachytherapy in the country. The special radiotherapy includes Gamma-knife, linac-based stereotactic radiosurgery, conformal radiotherapy and Intensity modulated radiotherapy. The nuclear data base has been completed on the basis of these data collected and the web site made is available with ease to anyone who want to get nuclear data. 39 refs., 20 figs., 8 tabs. (Author)

  4. Comprehensive Nuclear-Test-Ban Treaty: Background and Current Developments

    Science.gov (United States)

    2013-06-10

    09/205_119828.html; and Foster Klug and Matthew Pennington, “Photos Show NKorea Nuclear Readiness,” Associated Press/ ABC News, December 28, 2012, http...the CTBT, lack of Chinese ratification, U.S. efforts to seek renegotiation of the ABM Treaty, and efforts to ban nuclear weapons in the Middle East led...Readiness,” Associated Press/ ABC News, December 28, 2012, http://abcnews.go.com/International/wireStory/ap- exclusive-photos-show-nkorea-nuclear

  5. Grass-roots approach: developing qualified nuclear personnel

    Energy Technology Data Exchange (ETDEWEB)

    Nuclear power plants experiencing personnel recruitment problems are trying a grass-roots approach to increase the manpower pool. The Philadelphia Electric Co. and the Toledo Edison Co. are working with local educational institutions to offer nuclear-technology training specific to the needs of nuclear plants. The utilities' investment covers much of the cost of instruction as well as continued training for employees. (DCK)

  6. Development of an automated core model for nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Mosteller, R.D.

    1998-12-31

    This is the final report of a three-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). The objective of this project was to develop an automated package of computer codes that can model the steady-state behavior of nuclear-reactor cores of various designs. As an added benefit, data produced for steady-state analysis also can be used as input to the TRAC transient-analysis code for subsequent safety analysis of the reactor at any point in its operating lifetime. The basic capability to perform steady-state reactor-core analysis already existed in the combination of the HELIOS lattice-physics code and the NESTLE advanced nodal code. In this project, the automated package was completed by (1) obtaining cross-section libraries for HELIOS, (2) validating HELIOS by comparing its predictions to results from critical experiments and from the MCNP Monte Carlo code, (3) validating NESTLE by comparing its predictions to results from numerical benchmarks and to measured data from operating reactors, and (4) developing a linkage code to transform HELIOS output into NESTLE input.

  7. Next Generation Nuclear Plant Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    P. E. MacDonald

    2005-01-01

    The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission Demonstrate safe and economical nuclearassisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: High temperature gas reactor fuels behavior High temperature materials qualification Design methods development and validation Hydrogen production technologies Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen

  8. Development of undergraduate nuclear security curriculum at College of Engineering, Universiti Tenaga Nasional

    Science.gov (United States)

    Hamid, Nasri A.; Mujaini, Madihah; Mohamed, Abdul Aziz

    2017-01-01

    The Center for Nuclear Energy (CNE), College of Engineering, Universiti Tenaga Nasional (UNITEN) has a great responsibility to undertake educational activities that promote developing human capital in the area of nuclear engineering and technology. Developing human capital in nuclear through education programs is necessary to support the implementation of nuclear power projects in Malaysia in the near future. In addition, the educational program must also meet the nuclear power industry needs and requirements. In developing a certain curriculum, the contents must comply with the university's Outcomes Based Education (OBE) philosophy. One of the important courses in the nuclear curriculum is in the area of nuclear security. Basically the nuclear security course covers the current issues of law, politics, military strategy, and technology with regard to weapons of mass destruction and related topics in international security, and review legal regulations and political relationship that determine the state of nuclear security at the moment. In addition, the course looks into all aspects of the nuclear safeguards, builds basic knowledge and understanding of nuclear non-proliferation, nuclear forensics and nuclear safeguards in general. The course also discusses tools used to combat nuclear proliferation such as treaties, institutions, multilateral arrangements and technology controls. In this paper, we elaborate the development of undergraduate nuclear security course at the College of Engineering, Universiti Tenaga Nasional. Since the course is categorized as mechanical engineering subject, it must be developed in tandem with the program educational objectives (PEO) of the Bachelor of Mechanical Engineering program. The course outcomes (CO) and transferrable skills are also identified. Furthermore, in aligning the CO with program outcomes (PO), the PO elements need to be emphasized through the CO-PO mapping. As such, all assessments and distribution of Bloom Taxonomy

  9. Worldwide Report, Nuclear Development and Proliferation, No. 206.

    Science.gov (United States)

    2007-11-02

    explained, "the matter of safeguards has nothing to do with the ^ Argentine position of not signing the Tlatelolco Nuclear Nonproliferation Treaty. He...Energy indicates a complete change in the nuclear supply policy regarding Argentina as a result of the latter’s failure to sign the Tlatelolco

  10. Avoidable challenges of a nuclear medicine facility in a developing nation.

    Science.gov (United States)

    Adedapo, Kayode Solomon; Onimode, Yetunde Ajoke; Ejeh, John Enyi; Adepoju, Adewale Oluwaseun

    2013-10-01

    The role of nuclear medicine in disease management in a developing nation is as impactful as it is in other regions of the world. However, in the developing world, the practice of nuclear medicine is faced with a myriad of challenges, which can be easily avoided. In this review, we examine the many avoidable challenges to the practice of nuclear medicine in a developing nation. The review is largely based on personal experiences of the authors who are the pioneers and current practitioners of nuclear medicine in a typical developing nation. If the challenges examined in this review are avoided, the practice of nuclear medicine in such a nation will be more effective and practitioners will be more efficient in service delivery. Hence, the huge benefits of nuclear medicine will be made available to patients in such a developing nation.

  11. Development of nuclear fuel cycle technologies - bases of long-term provision of fuel and environmental safety of nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Solonin, M.I.; Polyakov, A.S.; Zakharkin, B.S.; Smelov, V.S.; Nenarokomov, E.A.; Mukhin, I.V. [SSC, RF, A.A. Bochvar ALL-Russia Research Institute of Inorganic Materials, Moscow (Russian Federation)

    2000-07-01

    To-day nuclear power is one of the options, however, to-morrow it may become the main source of the energy, thus, providing for the stable economic development for the long time to come. The availability of the large-scale nuclear power in the foreseeable future is governed by not only the safe operation of nuclear power plants (NPP) but also by the environmentally safe management of spent nuclear fuel, radioactive waste conditioning and long-term storage. More emphasis is to be placed to the closing of the fuel cycle in view of substantial quantities of spent nuclear fuel arisings. The once-through fuel cycle that is cost effective at the moment cannot be considered to be environmentally safe even for the middle term since the substantial build-up of spent nuclear fuel containing thousands of tons Pu will require the resolution of the safe management problem in the nearest future and is absolutely unjustified in terms of moral ethics as a transfer of the responsibility to future generations. The minimization of radioactive waste arisings and its radioactivity is only feasible with the closed fuel cycle put into practice and some actinides and long-lived fission radionuclides burnt out. The key issues in providing the environmentally safe fuel cycle are efficient processes of producing fuel for NPP, radionuclide after-burning included, a long-term spent nuclear fuel storage and reprocessing as well as radioactive waste management. The paper deals with the problems inherent in producing fuel for NPP with a view for the closed fuel cycle. Also discussed are options of the fuel cycle, its effectiveness and environmental safety with improvements in technologies of spent nuclear fuel reprocessing and long-lived radionuclide partitioning. (authors)

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

    Science.gov (United States)

    Geraskin, N. I.; Glebov, V. B.

    2017-01-01

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

  13. The Development of a Radiation Hardened Robot for Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Seung Ho; Kim, Chang Hoi; Seo, Yong Chil (and others)

    2007-04-15

    We has been developed two remotely controlled robotic systems. One is a underwater vehicle for inspection of the internal structures of PWRs and retrieving foreign stubs in the reactor pressure vessels and reactor coolant pipes. The other robotic system consists of a articulated-type mobile robot capable of recovering the failure of the fuel exchange machine and a mini modular mobile robot for inspection of feeder pipes with ultrasonic array sensors in PHWRs. The underwater robot has been designed by considering radiation effect, underwater condition, and accessibility to the working area. The size of underwater robot is designed to enter the cold legs. A extendable manipulator is mounted on the mobile robot, which can restore nuclear fuel exchange machine. The mini modular mobile robot is composed of dual inch worm mechanisms, which are constructed by two gripper bodies that can fix the robot body on to the pipe and move along the longitudinal and to rotate in a circumferential direction to access all of the outer surfaces of the pipe.

  14. Developing International Guidelines on Volcanic Hazard Assessments for Nuclear Facilities

    Science.gov (United States)

    Connor, Charles

    2014-05-01

    Worldwide, tremendous progress has been made in recent decades in forecasting volcanic events, such as episodes of volcanic unrest, eruptions, and the potential impacts of eruptions. Generally these forecasts are divided into two categories. Short-term forecasts are prepared in response to unrest at volcanoes, rely on geophysical monitoring and related observations, and have the goal of forecasting events on timescales of hours to weeks to provide time for evacuation of people, shutdown of facilities, and implementation of related safety measures. Long-term forecasts are prepared to better understand the potential impacts of volcanism in the future and to plan for potential volcanic activity. Long-term forecasts are particularly useful to better understand and communicate the potential consequences of volcanic events for populated areas around volcanoes and for siting critical infrastructure, such as nuclear facilities. Recent work by an international team, through the auspices of the International Atomic Energy Agency, has focused on developing guidelines for long-term volcanic hazard assessments. These guidelines have now been implemented for hazard assessment for nuclear facilities in nations including Indonesia, the Philippines, Armenia, Chile, and the United States. One any time scale, all volcanic hazard assessments rely on a geologically reasonable conceptual model of volcanism. Such conceptual models are usually built upon years or decades of geological studies of specific volcanic systems, analogous systems, and development of a process-level understanding of volcanic activity. Conceptual models are used to bound potential rates of volcanic activity, potential magnitudes of eruptions, and to understand temporal and spatial trends in volcanic activity. It is these conceptual models that provide essential justification for assumptions made in statistical model development and the application of numerical models to generate quantitative forecasts. It is a

  15. The development of advanced robotics for the nuclear industry -The development of robotic system for the nuclear power plants-

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seung Hoh; Kim, Chang Heui; Kim, Byung Soo; Hwang, Suk Yong; Kim, Kee Hoh; Lee, Jae Kyung; Lee, Yung Kwang; Suh, Yong Chil; Lee, Yong Bum; Kim, Woong Kee; Park, Soon Yong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    The Advanced Robotics Department of the Korea Atomic Energy Research Institute (KAERI) is developing a Dexterous Manipulation System (DMS) and a teleoperated mobile robot, identified as KAEROT/ml, for use in nuclear power plants. The DMS is being developed for performing tasks such as the opening and closing of nozzle dam inside water chamber of steam generator. The DMS has two major subsystems; a master-slave 6 degrees of freedom (dof) manipulator and a support device. The master-slave arms are designed dissimilar kinematically and dynamically, and their functions are performed by a bilateral force-reflecting force control. The slave is a hydraulically powered arm with a 3 dof end effector, and is mounted on the top of the support device for nozzle dam operation. The support device guides the slave arm into the water chamber and supports it during its operation. The DMS can be operated either in teleoperated or supervisory control modes. The KAEROT/ml is designed to be used in emergency response applications such as monitoring and mapping radiation areas, handling radioactive materials and performing decontamination tasks. The KAEROT/ml equipped with four-omnidirectional planetary wheels has a 6 dof joint-controlled arm and is capable of ascending and descending stairs and navigating flat surface with zero turning radius. This report describes the mechanical design, features, modeling and control system of both the DMS and the KAEROT/ml. 209 figs, 49 pix, 69 tabs, 62 refs. (Author).

  16. Nuclear Power Industry of China Enters a New Stage of Development

    Institute of Scientific and Technical Information of China (English)

    2005-01-01

    This article describes the basic conditions of nuclear power plants or projects in China, which have been built up, or under construction, or approved by the State Council. Excellent operating indexes of the existing nuclear power plants and the capability of independent design, manufacture, construction and operation are briefly enumerated.There are over thirty nuclear power plant sites in the coastal and inland areas, which have been checked or preevaluated. This proves that a solid foundation for large-scaled development of nuclear power industry has been laid and nuclear power will certainly play an important role in power supply and environment protection of China.

  17. Development of Fabrication Technology for Ceramic Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Kim, H. S.; Lee, Y. W.; Na, S. H.; Kim, Y. G.; Jung, C. Y.; Kim, S. H.; Lee, S. C.; Son, D. S

    2006-04-15

    Purpose and Necessity Research purposes for the 3rd stage were to reaffirm the MOX fabrication processes and to establish the process database, based on the fabrication technology developed during the previous stage. This project was also proceeded to improve the fuel performance and to accomplish the inherent MOX technology for PWR. The fabrication processes should be proceeded in the glove boxes because the raw powders of MOX fuel is very toxic. Therefore, some special technology were needed to develop besides the fuel fabrication technology. Both core technology and steadiness of fabrication process are important to obtain homogeneity and thermo-physical properties of MOX fuel pellet. By developing these technology in fashion unique to ourselves, we can take the initiative in the nuclear fuel for next generation. The uranium price has been increasing along with the oil price recently. We have to secure the MOX fabrication technology which serves the effective use of uranium resource. Improvement of pellet characteristics along with the MOX irradiation analysis: Collection and monitoring of the MOX irradiation data, Establishment of the improvement methods of pellet characteristics Establishment of the MOX pellet fabrication process by the unique technology, Establishment of database with the MOX fabrication parameters and characteristics, Analysis of co-relation and re-appearance of the pellet characteristics affected by each process parameter, Construction of feedback system between database and process, Application of the unique fabrication technology to the industrial spot. Applicability of the unique fabrication processes to the glove box technology, Installment of process equipment in the glove box and development of operation skill, Methods for modifying, handling, maintaining and fixing of glove box and subsidiary, Construction of transport channel for the connection between glove boxes - MOX fabrication by the unique technology in the glove box. Research

  18. Application Research of Developed Drummed Nuclear Waste Neutron Counting System

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The application researches such as variety of factors affecting the measurement, calibrating etc. are need before the drummed nuclear waste neutron counting system (WNC) can be really put into use after installed at the site.

  19. Nuclear propulsion technology development - A joint NASA/Department of Energy project

    Science.gov (United States)

    Clark, John S.

    1992-01-01

    NASA-Lewis has undertaken the conceptual development of spacecraft nuclear propulsion systems with DOE support, in order to establish the bases for Space Exploration Initiative lunar and Mars missions. This conceptual evolution project encompasses nuclear thermal propulsion (NTP) and nuclear electric propulsion (NEP) systems. A technology base exists for NTP in the NERVA program files; more fundamental development efforts are entailed in the case of NEP, but this option is noted to offer greater advantages in the long term.

  20. Nuclear propulsion technology development - A joint NASA/Department of Energy project

    Science.gov (United States)

    Clark, John S.

    1992-01-01

    NASA-Lewis has undertaken the conceptual development of spacecraft nuclear propulsion systems with DOE support, in order to establish the bases for Space Exploration Initiative lunar and Mars missions. This conceptual evolution project encompasses nuclear thermal propulsion (NTP) and nuclear electric propulsion (NEP) systems. A technology base exists for NTP in the NERVA program files; more fundamental development efforts are entailed in the case of NEP, but this option is noted to offer greater advantages in the long term.

  1. Nuclear liability coverage developments in the United States of America

    Energy Technology Data Exchange (ETDEWEB)

    Brown II, Omer F.

    1995-12-31

    The availability of such nuclear liability coverage has been a concern of nuclear power plant vendors, suppliers and operators, and public officials in the United States or many years. This paper addresses implications of the Federal Price-Anderson Act (42 U.S.C. 2014, 2020; Sections 11 and 170 of the Atomic Energy Act of 1954, as amended); on the financial liability of persons accountable for an accident in the United States. (author).

  2. Investigation on the 50 years of nuclear development in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kwang Seok; Oh, K. B.; Lee, B. W.; Ko, H. S.; Ryoo, J. S.; Seo, M. W.; Won, B. C

    2007-10-15

    Right persons, who are able to speak out the hidden history piled up in the cause of R and D and industrial applications in nuclear technology, are recommended and introduced. Forums for which senior members in the nuclear society have superintend are held with panel discussions on the topics requested. The hidden history traced out are openly discussed. Hidden historical materials uncovered are systematically compiled and subjected to be objectified.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-05-15

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

  4. The study on the development of nuclear cooperation policy and the follow-up of nuclear joint committee meeting between Korea and Vietnam

    Energy Technology Data Exchange (ETDEWEB)

    Yang, M. H.; Yun, S. W.; Jeong, I.; Choi, P. H.; Seo, M. W

    2004-02-01

    National efforts have been carried out positively to export nuclear technologies to oversee nuclear power markets, which can enable to contribute to enhance the national prestige and the promotion of cooperation foundation in international community. The demand of energy and electricity in Vietnam is continuously increasing due to rapid industrial development and economical development during the last several years. In order to meet the increasing electricity demand, Vietnam has been carrying out positive nuclear R and D and plans to introduce the first nuclear power plant between the year 2015 and 2010. It is necessary to strengthen the cooperative relations with Vietnam to introduce nuclear power plants as well as export of nuclear technologies through various channel such as the exchange of governmental cooperation delegation and the joint meeting of nuclear cooperation between Korea and Vietnam in field of peaceful use and development of nuclear energy between two countries.

  5. Simulation tools: development and application of nuclear projects; Herramientas de simulacion: desarrollo y aplicacion a proyectos nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Huelamo, E.; Perez Vara, R.; Arguello, A.; Garcia, M.

    2012-11-01

    In this paper we present some simulation models of system and equipment from nuclear power plants, builded-up with EcosimPro, a simulation tool created by Empresarios Agrupados. It was developed as a general simulation engine, as a tool devoted to the resolution of DAE's (ordinary differential and algebraic equations sets), doing abstraction of what physical system they represent. Component libraries must be added to the calculation engine, as needed by the discipline object of simulation, in order to be able of building up models. From first ECOSIM version there were already builded models applied to thermal and nuclear power plants. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-01-15

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

  7. Ion beam analysis - development and application of nuclear reaction analysis methods, in particular at a nuclear microprobe

    Energy Technology Data Exchange (ETDEWEB)

    Sjoeland, K.A.

    1996-11-01

    This thesis treats the development of Ion Beam Analysis methods, principally for the analysis of light elements at a nuclear microprobe. The light elements in this context are defined as having an atomic number less than approx. 13. The work reported is to a large extent based on multiparameter methods. Several signals are recorded simultaneously, and the data can be effectively analyzed to reveal structures that can not be observed through one-parameter collection. The different techniques are combined in a new set-up at the Lund Nuclear Microprobe. The various detectors for reaction products are arranged in such a way that they can be used for the simultaneous analysis of hydrogen, lithium, boron and fluorine together with traditional PIXE analysis and Scanning Transmission Ion Microscopy as well as photon-tagged Nuclear Reaction Analysis. 48 refs.

  8. Angra 1 nuclear power plant full scope simulator development project

    Energy Technology Data Exchange (ETDEWEB)

    Selvatici, Edmundo; Castanheira, Luiz Carlos C.; Silva Junior, Nilo Garcia da, E-mail: edsel@eletronuclear.gov.br, E-mail: lccast@eletronuclear.gov.br, E-mail: nilogar@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (SCO/ELETRONUCLEAR), Angra dos Reis, RJ (Brazil). Superintendencia de Coordenacao da Operacao; Zazo, Francisco Javier Lopez; Ruiz, Jose Antonio, E-mail: jlopez@tecnatom.es, E-mail: jaruiz@tecnatom.es [Tecnatom S.A., San Sebastian de los Reyes, Madrid (Spain)

    2015-07-01

    Specific Full Scope Simulators are an essential tool for training NPP control room operators, in the formation phase as well as for maintaining their qualifications. In the last years availability of a Plant specific simulator has also become a Regulator requirement for Nuclear Power Plant operation. By providing real-time practical training for the operators, the use of a simulator allows improving the operator's performance, reducing the number of unplanned shutdowns and more effective response to abnormal and emergency operating conditions. It can also be used, among other uses, to validate procedures, test proposed plant modifications, perform engineering studies and to provide operation training for the technical support staff of the plant. The NPP site, in Angra dos Reis-RJ, Brazil, comprises the two units in operation, Unit 1, 640 MWe, Westinghouse PWR and Unit 2, 1350 MWe, KWU/Areva PWR and one unit in construction, Unit 3, 1405 MWe, KWU/Areva PWR, of the same design of Angra 2. Angra 2 has had its full scope simulator from the beginning, however this was not the case of Angra 1, that had to train its operators abroad, due to lack of a specific simulator. Eletronuclear participated in all the phases of the project, from data supply to commissioning and validation. The Angra 1 full scope simulator encompasses more than 80 systems of the plant including the Primary system, reactor core and associated auxiliary systems, the secondary system and turbo generator as well as all the Plant operational and safety I and C. The Angra 1 Main Control Room panels were reproduced in the simulator control room as well as the remote shutdown panels that are outside the control room. This paper describes the project for development of the Angra 1 NPP Full Scope Simulator, supplied by Tecnatom S.A., in the period of Feb.2012 to Feb.2015. (author)

  9. Spore development and nuclear inheritance in arbuscular mycorrhizal fungi

    Directory of Open Access Journals (Sweden)

    Hijri Mohamed

    2011-02-01

    Full Text Available Abstract Background A conventional tenet of classical genetics is that progeny inherit half their genome from each parent in sexual reproduction instead of the complete genome transferred to each daughter during asexual reproduction. The transmission of hereditary characteristics from parents to their offspring is therefore predictable, although several exceptions are known. Heredity in microorganisms, however, can be very complex, and even unknown as is the case for coenocytic organisms such as Arbuscular Mycorrhizal Fungi (AMF. This group of fungi are plant-root symbionts, ubiquitous in most ecosystems, which reproduce asexually via multinucleate spores for which sexuality has not yet been observed. Results We examined the number of nuclei per spore of four AMF taxa using high Z-resolution live confocal microscopy and found that the number of nuclei was correlated with spore diameter. We show that AMF have the ability, through the establishment of new symbioses, to pass hundreds of nuclei to subsequent generations of multinucleated spores. More importantly, we observed surprising heterogeneity in the number of nuclei among sister spores and show that massive nuclear migration and mitosis are the mechanisms by which AMF spores are formed. We followed spore development of Glomus irregulare from hyphal swelling to spore maturity and found that the spores reached mature size within 30 to 60 days, and that the number of nuclei per spores increased over time. Conclusions We conclude that the spores used for dispersal of AMF contain nuclei with two origins, those that migrate into the spore and those that arise by mitosis in the spore. Therefore, these spores do not represent a stage in the life cycle with a single nucleus, raising the possibility that AMF, unlike all other known eukaryotic organisms, lack the genetic bottleneck of a single-nucleus stage.

  10. Economics of Nuclear Power Plant and the development of nuclear power in Viet Nam

    Energy Technology Data Exchange (ETDEWEB)

    Thanh, Thuy Nguyen Thi; Song, JinHo [University of Science and Technology, Daejeon (Korea, Republic of); Ha, Kwang Soon [KAERI, Daejeon (Korea, Republic of)

    2015-05-15

    There are many factors affecting the capital costs like: increased plant size, multiple unit construction, improved construct methods, increase the lifetime of plant and so on, and beside is technical to enhancing the safety for NPPs. For the question that whether building a NPP is really economic than other energy resources or not, we will find the answer by comparing the USD per kWh of different energy sources as: nuclear power, coal, oil, hydro natural energy sources. The situation of energy in Vietnam was also mentioned in this paper. Vietnam has an abundant natural resources likes: coal, gas, hydro power etc, but from year 2013 to now Vietnam facing of electricity shortage and to solve the problem, Vietnam Government has chosen nuclear power energy to achieve energy balance between the rate of energy consumption and the ability to energy supply. Eight units will be built in Vietnam and in October 2014 Vietnamese officials have chosen Rosatom's AES-2006 design with VVER-1200/v-491 reactors for country's first nuclear power plant at Ninh Thuan and a second plant should follow based on a partnership with Japan. In this paper, the breakdown of NPP costs is considered. All the costs for building a NPP includes: the investment costs are the largest components (about 60%), fuel costs (15%), O and M costs (25%) and external costs are lower than 1% of the kWh costs. The situation for energy in Vietnam was mentioned with increase annually by 5.5 %, and now the shortage electricity is the big problem in power section. The purpose of this report is to give a general picture to consider the cost of nuclear power. It includes all the costs for building a nuclear power plant like total capital investment costs, production costs, external costs in which the capital investment costs is the largest component of the kWh cost. Nuclear energy Power was chosen to deal with situation of diminishing resources shortages.

  11. FRENDY: A new nuclear data processing system being developed at JAEA

    Science.gov (United States)

    Tada, Kenichi; Nagaya, Yasunobu; Kunieda, Satoshi; Suyama, Kenya; Fukahori, Tokio

    2017-09-01

    JAEA has provided an evaluated nuclear data library JENDL and nuclear application codes such as MARBLE, SRAC, MVP and PHITS. These domestic codes have been widely used in many universities and industrial companies in Japan. However, we sometimes find problems in imported processing systems and need to revise them when the new JENDL is released. To overcome such problems and immediately process the nuclear data when it is released, JAEA started developing a new nuclear data processing system, FRENDY in 2013. This paper describes the outline of the development of FRENDY and both its capabilities and performances by the analyses of criticality experiments. The verification results indicate that FRENDY properly generates ACE files.

  12. Training requirements for chemists in radiotracer development for nuclear medicine

    Energy Technology Data Exchange (ETDEWEB)

    Finn, R.; Fowler, J.

    1988-01-01

    This panel was organized to address the current and anticipated future shortage of chemists with advanced training to fill positions in the nuclear medicine field. Although hard data and statistics are difficult to acquire, we will attempt to highlight the impact of chemistry on nuclear medicine and to describe the growth of the field which has led to an increasing need for chemists resulting in the current manpower shortage. We also will make recommendations for attracting Ph.D. chemists to careers in nuclear medicine research and possible mechanisms for postgraduate training. Solving this problem and establishing a long term committment and mechanism for advanced training is critically important to meet the current needs of the profession and to assure future growth and innovation. 3 tabs.

  13. A study on the planning for the research and development of nuclear energy

    Energy Technology Data Exchange (ETDEWEB)

    Noh, Byong Chull; Won, B. C.; Bang, J. K.; Jung, Y. H.; Kim, M. R.; Cho, C. Y.; Lee, H. S.; Kim, J. U.; Yeo, J. W.; Hong, Y. P.; Kim, I. C.; Rha, K. H.; Yoon, Y. S.; Park, J. H.; Ko, Y. S.; Kim, S. S.; Kang, W. J.; Lee, Y. H.; Shim, H. W.

    1997-01-01

    This study has performed aiming to provide the government with the basic input to establish `the comprehensive promotion plan for utilization, research and development of nuclear energy` and `the mid- and long-term nuclear research and development program`, thus the government set it up as a national plan after endorsement of Atomic Energy Commission. Next, the feasibility study of the proton accelerators construction which is expected to use for nuclear research and development and industry. And a systematic and integrated research and development management system for the large-scale projects has been studied considering the inherent uncertainty and high risk of research and development. (author). 24 tabs., 6 figs.

  14. A study on the planning for the research and development of nuclear energy

    Energy Technology Data Exchange (ETDEWEB)

    Noh, Byong Chull; Won, B. C.; Bang, J. K.; Jung, Y. H.; Kim, M. R.; Cho, C. Y.; Lee, H. S.; Kim, J. U.; Yeo, J. W.; Hong, Y. P.; Kim, I. C.; Rha, K. H.; Yoon, Y. S.; Park, J. H.; Ko, Y. S.; Kim, S. S.; Kang, W. J.; Lee, Y. H.; Shim, H. W.

    1997-01-01

    This study has performed aiming to provide the government with the basic input to establish `the comprehensive promotion plan for utilization, research and development of nuclear energy` and `the mid- and long-term nuclear research and development program`, thus the government set it up as a national plan after endorsement of Atomic Energy Commission. Next, the feasibility study of the proton accelerators construction which is expected to use for nuclear research and development and industry. And a systematic and integrated research and development management system for the large-scale projects has been studied considering the inherent uncertainty and high risk of research and development. (author). 24 tabs., 6 figs.

  15. U.S. Strategic Nuclear Forces: Background, Developments, and Issues

    Science.gov (United States)

    2016-03-10

    committed to accelerating and completing the program. According to press reports, the Air Force plans to buy a total of 1,000-1,100 new cruise missiles...program follows the trends set by previous bomber programs. 131 The per-unit cost of $550 million would also rise if the Air Force were to buy fewer...Boredom, Drugs, Low Morale. The millennials of the U.S. nuclear missile corps are struggling to stay on high alert for a nuclear Armageddon,” Slate

  16. Next Generation Nuclear Plant Materials Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    G. O. Hayner; E.L. Shaber

    2004-09-01

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years.

  17. International Source Book: Nuclear Fuel Cycle Research and Development Vol 1 Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, K. M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lakey, L. T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    1983-07-01

    This document starts with an overview that summarizes nuclear power policies and waste management activities for nations with significant commercial nuclear fuel cycle activities either under way or planned. A more detailed program summary is then included for each country or international agency conducting nuclear fuel cycle and waste management research and development. This first volume includes the overview and the program summaries of those countries listed alphabetically from Argentina to Italy.

  18. Formulating Human Resources Development Strategies for Nuclear R and D, Safety and Security

    Energy Technology Data Exchange (ETDEWEB)

    Min, B. J.; Kim, M. K.; Son, M. Y.

    2010-05-15

    Enforced by the recent launch of the 4th National Power Expansion Plan and the 1st Basic Plan for National Energy Policy with an ambitious goal of achieving 'Low CO2 Emission and Green Growth', a rapid expansion of nuclear technology development has been reemphasized. In addition, the nation, being a potential exporter of nuclear power plants and nuclear technologies strives to explore their exports markets. In response, it is inevitable to set the priority in human resource development (HRD) as nuclear technology development both requires and fosters HRD which in turn, enables to meet the successful implementation of nuclear power expansion. A continuous, consistent and well-managed programme of HRD is crucial to assure continuity over time in the needed capacities, skills and knowledge, and to establish and maintain a cadre of manpower variously trained in different nuclear-related skills and educated in nuclear relevant fields. The objective of the study is to conduct comprehensive quantitative analyses to estimate future human resources requirements, particularly in the field of nuclear R and D, safety and security in order to establish an appropriate long-term nuclear HRD plan

  19. The alternative strategies of the development of the nuclear power industry in the 21st century

    Science.gov (United States)

    Goverdovskii, A. A.; Kalyakin, S. G.; Rachkov, V. I.

    2014-05-01

    This paper emphasizes the urgency of scientific-and-technical and sociopolitical problems of the modern nuclear power industry without solving of which the transition from local nuclear power systems now in operation to a large-scale nuclear power industry would be impossible. The existing concepts of the longterm strategy of the development of the nuclear power industry have been analyzed. On the basis of the scenarios having been developed it was shown that the most promising alternative is the orientation towards the closed nuclear fuel cycle with fast neutron reactors (hereinafter referred to as fast reactors) that would meet the requirements on the acceptable safety. It was concluded that the main provisions of "The Strategy of the Development of the Nuclear Power Industry of Russia for the First Half of the 21st Century" approved by the Government of the Russian Federation in the year 2000 remain the same at present as well, although they require to be elaborated with due regard for new realities in the market for fossil fuels, the state of both the Russian and the world economy, as well as tightening of requirements related to safe operation of nuclear power stations (NPSs) (for example, after the severe accident at the Fukushima nuclear power station, Japan) and nonproliferation of nuclear weapons.

  20. The role of nuclear reactors in space exploration and development

    Energy Technology Data Exchange (ETDEWEB)

    Lipinski, R.J.

    2000-07-01

    The United States has launched more than 20 radioisotopic thermoelectric generators (RTGs) into space over the past 30 yr but has launched only one nuclear reactor, and that was in 1965. Russia has launched more than 30 reactors. The RTGs use the heat of alpha decay of {sup 238}Pu for power and typically generate <1 kW of electricity. Apollo, Pioneer, Voyager, Viking, Galileo, Ulysses, and Cassini all used RTGs. Space reactors use the fission energy of {sup 235}U; typical designs are for 100 to 1000 kW of electricity. The only US space reactor launch (SNAP-10A) was a demonstration mission. One reason for the lack of space reactor use by the United States was the lack of space missions that required high power. But, another was the assumed negative publicity that would accompany a reactor launch. The net result is that all space reactor programs after 1970 were terminated before an operating space reactor could be developed, and they are now many years from recovering the ability to build them. Two major near-term needs for space reactors are the human exploration of Mars and advanced missions to and beyond the orbit of Jupiter. To help obtain public acceptance of space reactors, one must correct some of the misconceptions concerning space reactors and convey the following facts to the public and to decision makers: Space reactors are 1000 times smaller in power and size than a commercial power reactor. A space reactor at launch is only as radioactive as a pile of dirt 60 m (200 ft) across. A space reactor contains no plutonium at launch. It does not become significantly radioactive until it is turned on, and it will be engineered so that no launch accident can turn it on, even if that means fueling it after launch. The reactor will not be turned on until it is in a high stable orbit or even on an earth-escape trajectory for some missions. The benefits of space reactors are that they give humanity a stairway to the planets and perhaps the stars. They open a new

  1. Model development for quantitative evaluation of proliferation resistance of nuclear fuel cycles

    Energy Technology Data Exchange (ETDEWEB)

    Ko, Won Il; Kim, Ho Dong; Yang, Myung Seung

    2000-07-01

    This study addresses the quantitative evaluation of the proliferation resistance which is important factor of the alternative nuclear fuel cycle system. In this study, model was developed to quantitatively evaluate the proliferation resistance of the nuclear fuel cycles. The proposed models were then applied to Korean environment as a sample study to provide better references for the determination of future nuclear fuel cycle system in Korea. In order to quantify the proliferation resistance of the nuclear fuel cycle, the proliferation resistance index was defined in imitation of an electrical circuit with an electromotive force and various electrical resistance components. The analysis on the proliferation resistance of nuclear fuel cycles has shown that the resistance index as defined herein can be used as an international measure of the relative risk of the nuclear proliferation if the motivation index is appropriately defined. It has also shown that the proposed model can include political issues as well as technical ones relevant to the proliferation resistance, and consider all facilities and activities in a specific nuclear fuel cycle (from mining to disposal). In addition, sensitivity analyses on the sample study indicate that the direct disposal option in a country with high nuclear propensity may give rise to a high risk of the nuclear proliferation than the reprocessing option in a country with low nuclear propensity.

  2. International political environment for the research and development of nuclear fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Young Sun [Seoul National University, Seoul (Korea, Republic of)

    1997-05-01

    The international acceptance of South Korea`s nuclear fuel cycle technology as a peaceful use of nuclear energy needs peaceful relations between South and North Korea. Thus, this study examines the current North Korea`s policy toward South Korea as a part of North Korea`s three-fold survival strategy in the post-cold war period and also forecasts future relations between two countries on the Korean peninsula. To cope with nuclear= nonproliferation policy of the United Sates successfully, which does not allow South Korea`s autonomous nuclear fuel cycle, this study reviews the history of Washington`s nuclear nonproliferation policy with case studies of South Korea`s reprocessing plant project in the 1970`s, US-Japan Nuclear Cooperation Agreement in the 1980`s, and North Korea`s nuclear program in the 1990`s, and for casts the future on nuclear nonproliferation policy of the United States. In conclusion, this analysis tries to develop new approaches to solve two major problems of Korean situation and nuclear nonproliferation policy of the United Sates for the autonomous nuclear fuel cycle in South Korea. (Author) 33 refs.

  3. Upgradation of nuclear medical equipment in the developing countries and its impact in Bangladesh

    CERN Document Server

    Jahangir, S M; Haque, M A S; Hoq, M; Mawla, Y; Morium, T; Uddin, M R; Xie, Y

    2002-01-01

    Bangladesh has thirteen Nuclear Medical Centres and one Institute of Nuclear Medicine in the country which are being run and maintained by the physicians scientists and engineers of Bangladesh Atomic Energy Commission. The peaceful application of atomic energy was initiated through all these Centres with the use of clinical isotopes for thyroid and kidney studies. The equipment used for these purposes were the thyroid uptake system, rectilinear scanner and the multiprobe renogram system. The first gamma camera was installed in the country in 1980 at the Institute of Nuclear Medicine, Dhaka. That was the turning point for the country in the field of nuclear medicine. Presently all the nuclear medical establishments are equipped least with a gamma camera, thyroid uptake system and a renogram system. In the last two decades there has been a tremendous development in the design of nuclear medical equipment. Most of the old equipments were slow and manually operated. In the beginning of nineties of the past centur...

  4. A study on the research and development planning of nuclear energy

    Energy Technology Data Exchange (ETDEWEB)

    Noh, Byong Chull; Won, B. C.; Kim, J. W.; Cho, C. Y.; Cheon, S. H.; Kim, J. U.; Kim, I. C.; Hong, Y. P.; Kang, W. J.; Lee, H. S.; Yoon, Y. S.; Park, J. H.; Kim, S. S.; Park, C. S.; Yang, M. S.; Lee, Y. H

    1998-01-01

    This study was performed aiming to provide the basic input to establish `the mild and long-term nuclear R and D program (1997 - 2006)` for government. This program is announced by the government as an official plan after endorsement of Atomic Energy Commission (AEC). Second, the historical formation and transition of both nuclear R and D policy and nuclear R and D development system after the introduction of nuclear energy in Korea were analyzed. Third, the current status of several nuclear-related R and D projects and R and D management, which have been conducted at KAERI were analyzed and a better direction for effective and efficient R and D activities was suggested. Finally, on the basis of above analysis, this study made an effort to extract the appropriate lessons for future directions for carrying out nuclear R and D projects. (author). 19 refs., 40 tabs., 10 figs

  5. Current Status and Future Perspective of Nuclear Energy Human Resource Development

    Science.gov (United States)

    Yamamoto, Shinji

    In recent years, expectations for nuclear energy have been increasing in Japan because of its role and responsibility as a key power source, the contribution it can make to a global nuclear renaissance, the need for energy security, and the importance of combating global warming. Ensuring and fostering good human resources is essential if the nuclear industry is to maintain itself and expand its scale. There are obstacles, however, in doing so : a declining birth rate, job-hunting problem, the wave of retirements in 2007, the declining popularity of engineering departments and particularly nuclear-related subjects, a weakening of nuclear education, and deteriorating research facilities and equipment. While nuclear-related academic, industrial and governmental parties share this recognition and are cooperating and collaborating, all organizations are expected similarly to continue their own wholehearted efforts at human resource development.

  6. Feasibility Study on the Development of Index that Shows Social and Cultural Acceptance of Nuclear Power

    Energy Technology Data Exchange (ETDEWEB)

    Cho, SeongKyung [Bangmok College of General Education at Myongji Univ., Yongin (Korea, Republic of); Choi, Seungho; Yoon, Hana; Song, Jiyeon [Domo Brodeur, Seoul (Korea, Republic of)

    2015-05-15

    In this context, it is necessary to manage and develop an index that can measure the level of public acceptance by establishing the terms of social/cultural public acceptance of nuclear power in a practical manner and by identifying influential factors of public acceptance. Developing an index itself is not intended to increase the public acceptance of nuclear power. This study intends to contribute to determining energy policy acceptable to the public by estimating the level of potential social conflicts related to nuclear power policies with eligible evaluation criteria on social/cultural acceptance and by reducing relevant social costs. Key conclusions and proposal of this research are as follows. First, the influential factors of acceptance are reliability of nuclear safety, risk perception of nuclear power and beneficial perception of nuclear power. Among them, reliability of nuclear safety appears to have the most influence. In addition, benefit perception of nuclear power at the social level is significantly higher than that at the individual level. However, in relation to risk perception, a gap between experts and the public is found as nuclear industry premises that accident does not occur while the public premises that accident may occur.

  7. Comparative Analysis of the Indian and Pakistani Nuclear Energy Development Programmes

    Directory of Open Access Journals (Sweden)

    A. A. Boyko

    2015-01-01

    Full Text Available Due to the traditional competition between India and Pakistan, their strategic fields developing are interdependent. Nuclear power development programs are concerned as well. Pakistan falls behind India in this branch, however the specifics of the nuclear infrastructure let the potential of the states be relatively balanced. After Nuclear Suppliers Group granted a waiver to India in 2008 and Russia, France and USA, the new participants, broke into the market, India obtained an opportunity to make a breakthrough in the national nuclear program development, thus violating a status quo in fuel cycle technologies. Such chances stimulated China to violate the NSG guidelines and non-proliferations principles to get involved in Pakistani nuclear program development. The nuclear power Indian-Pakistani competition prospects largely depend on the Chinese position. Despite the international community suspects the Pakistani officials in nuclear black market dealing and the NSG guidelines China obviously supports the Pakistani nuclear field. This may result in preventing of escalation of tensions in the region. 

  8. Development of Noncontact Imaging Technology for the Detection of Internal Defects of a Nuclear Fuel Plate

    Energy Technology Data Exchange (ETDEWEB)

    Park, S. K.; Baik, S. H.; Lee, Y. S.; Cheong, Y. M.

    2012-01-15

    The object of the research is to develop a new imaging inspection technology for the quality testing of plate-type nuclear fuel whose demanding is currently increasing in nuclear research reactors. A new noncontact imaging inspection technique is developed for the detection of internal defects in plate-type nuclear fuel. To develop the imaging inspection technique, a hardware system based on active optical interference is configured. An operating software for the developed nondestructive inspection system is developed after designing an advanced signal processing algorithm to improve the detection capability of the system. The developed system is optimized through experiments and optimal heating condition is studied. The performance of a lock-in thermography is also evaluated to see the possibility of the plate-type nuclear fuel application.

  9. Nuclear Terrorism: Assessing the Threat, Developing a Response

    Science.gov (United States)

    2009-01-01

    separated plutonium might be found at civilian reprocessing facilities or mixed oxide ( MOX ) fuel fabrication plants, but this material would likely be in...2008. 165 Potter and Ferguson, The Four Faces of Nuclear Terrorism, p. 121. MOX reactor fuel contains approxi- mately four to seven percent...stealing spent power reactor fuel or fresh (unirradiated) MOX fuel, both of which would need to have their plutonium chemically extracted. While separating

  10. North Korea’s Nuclear Weapons Development and Diplomacy

    Science.gov (United States)

    2010-01-05

    States that have been frozen since the Korean War .29 Removal from the U.S. list of state sponsors of terrorism will end the requirement that U.S...normalization of relationships, a permanent peace regime [to replace the 1953 Korean War armistice] and significant energy and economic assistance.” Such a...Iranian nuclear facilities at Natanz and Irak . It issued a report in February 2008 that gave reputed details of North Korean-Iranian collaboration in

  11. FEL development at the Budker Institute of Nuclear Physics

    Science.gov (United States)

    Vinokurov, N. A.

    1993-07-01

    There are three different FEL projects at the Budker Institute of Nuclear Physics: 1) the FEL on the VEPP-3 storage ring which operates in the visible and ultraviolet region; 2) the high power FEL using a racetrack microtron recuperator (this machine will provide an average power of about tens of kilowatt in the infrared region); and 3) the compact infrared FEL project, using a microton, and a powerful FEL on a dedicated superconducting storage ring, which is under consideration now.

  12. U.S. Strategic Nuclear Forces: Background, Developments, and Issues

    Science.gov (United States)

    2015-03-18

    Library of Congress,101 Independence Ave, SE,Washington,DC,20540 8. PERFORMING ORGANIZATION REPORT NUMBER 9. SPONSORING/MONITORING AGENCY NAME(S) AND...Elaine M. Grossman, “Nuclear Bomb Update Effort Slowed by Posture Review, Science Studies,” Global Security Newswire, January 19, 2010. 91 U.S...between $20 and $45 billion if the program follows the trends set by previous bomber programs.119 The per- unit cost of $550 million would also rise if

  13. Development of regional network for nuclear information in Latin America

    Science.gov (United States)

    Ebinuma, Yukio

    Among the recent INIS activities several interesting items are reported. In particular Latin America area where active movements have been seen recently is described in detail in terms of INIS information services. The author reports Latin America regional nuclear information project which has been implemented as 5-year project since 1985 supported by IAEA, and its progress, and describes information service system in Brazil which plays the core role in promoting this project.

  14. U.S. Strategic Nuclear Forces: Background, Developments, and Issues

    Science.gov (United States)

    2017-02-10

    1,550 deployed warheads in 2018, after the New START Treaty completes implementation. At the present time, the U.S. land-based ballistic missile force...Structure and Size During the Cold War ......................................................................... 2 Force Structure and Size After the Cold...abandon the strategy of nuclear deterrence that has served as a core concept in U.S. national security strategy for more than 60 years. In a speech in

  15. Advanced Elastic/Inelastic Nuclear Data Development Project

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, Frank; Chowdhury, Partha; Greife, Uwe; Fisher Hicks, Sally; Tsvetkov, Pavel; Rahn Vanhoy, Jeffrey; Hill, Tony; Kawano, Toshihiko; Slaughter, David

    2015-06-08

    The optical model is used to analyze the elastic and inelastic scattering of nucleons, deuterons, hellions, tritons, and alpha particles by the nuclei. Since this paper covers primarily neutron-nucleus scattering, the focus will be limited to only that interaction. For the sake of this model, the nucleus is described as a blob of nuclear matter with properties based upon its number of nucleons. This infers that a single potential can describe the interaction of particles with different energies with different nuclei.

  16. The development of VR technology for nuclear industry applications

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong Bum; Cho, Jai Wan; Lee, Nam Ho; Choi, Young Soo; Park, Soon Yong

    1998-01-01

    By searching the present condition of virtual reality technology of which researches were carried out not only abroad but also the country in nuclear power industry, we confirm the possibility of practical usage of VR in it. And as a fundamental research for applications of VR in nuclear power industry, gesture recognition for remote working and VR training system for severe working were performed. 1. A study on gesture recognition for remote working : The hand gesture recognition technology using visual signal and tactile magnetic sensor as a basic study for the introduction of task command and communication were performed. 2. A study on an construction of the virtual environment training system for the task in a severe condition: A construction of virtual reality training system for the tasks in a severe working condition was implemented. This system was intended to enhance the efficiency of actual tasks through advanced practicing the motion procedures those should be performed in a severe working condition where it is difficult to access for personnel. The motion information which is came from the sensors attached on trainers body was used for construction of the virtual environment through the computer graphic procedures. The VR training system has many merits relative to the conservative training method that was performed with mock-up which was made as the same size and shape as real component in nuclear power plant. (author). 27 refs., 21 tabs., 51 figs

  17. Human resource development for nuclear generation - from the perspective of a utility company

    Science.gov (United States)

    Kahar, Wan Shakirah Wan Abdul; Mostafa, Nor Azlan; Salim, Mohd Faiz

    2017-01-01

    Malaysia is currently in the planning phase of its nuclear power program, with the first unit targeted to be operational in 2030. Training of nuclear power plant (NPP) staffs are usually long and rigorous due to the complexity and safety aspects of nuclear power. As the sole electricity utility in the country, it is therefore essential that Tenaga Nasional Berhad (TNB) prepares early in developing its human resource and nuclear expertise as a potential NPP owner-operator. A utility also has to be prudent in managing its work force efficiently and effectively, while ensuring that adequate preparations are being made to acquire the necessary nuclear knowledge with sufficient training lead time. There are several approaches to training that can be taken by a utility company with no experience in nuclear power. These include conducting feasibility studies and benchmarking exercises, preparing long term human resource development, increasing the exposure on nuclear power technology to both the top management and general staff, and employing the assistance of relevant agencies locally and abroad. This paper discusses the activities done and steps taken by TNB in its human resource development for Malaysia's nuclear power program.

  18. The development of advanced robotics for the nuclear industry -The development of advanced robotic technology-

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jong Min; Lee, Yong Bum; Park, Soon Yong; Cho, Jae Wan; Lee, Nam Hoh; Kim, Woong Kee; Moon, Byung Soo; Kim, Seung Hoh; Kim, Chang Heui; Kim, Byung Soo; Hwang, Suk Yong; Lee, Yung Kwang; Moon, Je Sun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    Main activity in this year is to develop both remote handling system and telepresence techniques, which can be used for people involved in extremely hazardous working area to alleviate their burden. In the robot vision technology part, KAERI-PSM system, stereo imaging camera module, stereo BOOM/MOLLY unit, and stereo HMD unit are developed. Also, autostereo TV system which falls under the category of next generation stereo imaging technology has been studied. The performance of KAERI-PSM system for remote handling task is evaluated and compared with other stereo imaging systems as well as general TV imaging system. The result shows that KAERI-PSM system is superior to the other stereo imaging systems about remote operation speedup and accuracy. The automatic recognition algorithm of instrument panel is studied and passive visual target tracking system is developed. The 5 DOF camera serving unit has been designed and fabricated. It is designed to function like human`s eye. In the sensing and intelligent control research part, thermal image database system for thermal image analysis is developed and remote temperature monitoring technique using fiber optics is investigated. And also, two dimensional radioactivity sensor head for radiation profile monitoring system is designed. In the part of intelligent robotics, mobile robot is fabricated and its autonomous navigation using fuzzy control logic is studied. These remote handling and telepresence techniques developed in this project can be applied to nozzle-dam installation/removal robot system, reactor inspection unit, underwater nuclear pellet inspection and pipe abnormality inspection. And these developed remote handling and telepresence techniques will be applied in general industry, medical science, and military as well as nuclear facilities. 203 figs, 12 tabs, 72 refs. (Author).

  19. 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.

  20. 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.

  1. Partnering for nuclear power development in Asia-pacific countries

    Energy Technology Data Exchange (ETDEWEB)

    Kugler, Gary [Atomic Energy of Canada Limited, Ottawa (Canada)

    1996-04-15

    KEPCO President Rieh remarked in a recent interview that the nature of nuclear technology itself highlights the need for international co-operation. The problems and solutions are global in nature. I would, respectfully, like to add my own thoughts on this subject through this paper. The Canadian writer, Marshall McLuhan, has the view of a global village where we are all virtual neighbours. International trade, telecommunications, the Internet all make it so. But there are deep-rooted regional bonds, ties that bind next dor neighbours.

  2. Comprehensive Nuclear-Test-Ban Treaty: Background and Current Developments

    Science.gov (United States)

    2008-05-28

    considers a U.S. contribution to a global system to monitor events that might violate the CTBT. The FY2008 appropriation was $23.8 million; the FY2009...ratified the CTBT. On December 17, 2007, Representative Tauscher introduced H.Res. 882, “[e] xpressing the sense of the House of Representatives that...Limited, January 13, 2007. 26 “Indian Lawmakers Attack U.S. Nuclear Deal,” Global Security Newswire, November 29, 2007. 27 Kathy Gannon, “New Pakistani

  3. A Programmatic and Engineering Approach to the Development of a Nuclear Thermal Rocket for Space Exploration

    Science.gov (United States)

    Bordelon, Wayne J., Jr.; Ballard, Rick O.; Gerrish, Harold P., Jr.

    2006-01-01

    With the announcement of the Vision for Space Exploration on January 14, 2004, there has been a renewed interest in nuclear thermal propulsion. Nuclear thermal propulsion is a leading candidate for in-space propulsion for human Mars missions; however, the cost to develop a nuclear thermal rocket engine system is uncertain. Key to determining the engine development cost will be the engine requirements, the technology used in the development and the development approach. The engine requirements and technology selection have not been defined and are awaiting definition of the Mars architecture and vehicle definitions. The paper discusses an engine development approach in light of top-level strategic questions and considerations for nuclear thermal propulsion and provides a suggested approach based on work conducted at the NASA Marshall Space Flight Center to support planning and requirements for the Prometheus Power and Propulsion Office. This work is intended to help support the development of a comprehensive strategy for nuclear thermal propulsion, to help reduce the uncertainty in the development cost estimate, and to help assess the potential value of and need for nuclear thermal propulsion for a human Mars mission.

  4. Nuclear Thermal Propulsion (NTP) Development Activities at the NASA Marshall Space Flight Center - 2006 Accomplishments

    Science.gov (United States)

    Ballard, Richard O.

    2007-01-01

    In 2005-06, the Prometheus program funded a number of tasks at the NASA-Marshall Space Flight Center (MSFC) to support development of a Nuclear Thermal Propulsion (NTP) system for future manned exploration missions. These tasks include the following: 1. NTP Design Develop Test & Evaluate (DDT&E) Planning 2. NTP Mission & Systems Analysis / Stage Concepts & Engine Requirements 3. NTP Engine System Trade Space Analysis and Studies 4. NTP Engine Ground Test Facility Assessment 5. Non-Nuclear Environmental Simulator (NTREES) 6. Non-Nuclear Materials Fabrication & Evaluation 7. Multi-Physics TCA Modeling. This presentation is a overview of these tasks and their accomplishments

  5. Developing a Hierarchical Decision Model to Evaluate Nuclear Power Plant Alternative Siting Technologies

    Science.gov (United States)

    Lingga, Marwan Mossa

    A strong trend of returning to nuclear power is evident in different places in the world. Forty-five countries are planning to add nuclear power to their grids and more than 66 nuclear power plants are under construction. Nuclear power plants that generate electricity and steam need to improve safety to become more acceptable to governments and the public. One novel practical solution to increase nuclear power plants' safety factor is to build them away from urban areas, such as offshore or underground. To date, Land-Based siting is the dominant option for siting all commercial operational nuclear power plants. However, the literature reveals several options for building nuclear power plants in safer sitings than Land-Based sitings. The alternatives are several and each has advantages and disadvantages, and it is difficult to distinguish among them and choose the best for a specific project. In this research, we recall the old idea of using the alternatives of offshore and underground sitings for new nuclear power plants and propose a tool to help in choosing the best siting technology. This research involved the development of a decision model for evaluating several potential nuclear power plant siting technologies, both those that are currently available and future ones. The decision model was developed based on the Hierarchical Decision Modeling (HDM) methodology. The model considers five major dimensions, social, technical, economic, environmental, and political (STEEP), and their related criteria and sub-criteria. The model was designed and developed by the author, and its elements' validation and evaluation were done by a large number of experts in the field of nuclear energy. The decision model was applied in evaluating five potential siting technologies and ranked the Natural Island as the best in comparison to Land-Based, Floating Plant, Artificial Island, and Semi-Embedded plant.

  6. Establishment of nuclear knowledge-information base; development of courseware on introductory nuclear engineering and establishment of digital education platform

    Energy Technology Data Exchange (ETDEWEB)

    Song, Jong Soon; Na, Mang Yun; Lee, Goung Jin; Yang, Won Sik [Chosun University, Gwangju (Korea)

    2002-01-01

    In this research, there are two major tasks. The first one is a development of digital course-ware program for introductory nuclear engineering. For this task, a development of lecture note is followed by lecture Slide files in html file format, which is based on web. For this purpose, following activities were performed; collection of related materials. planning of overall courseware, writing of lecture note and exercise plan, and securing the computer programs and codes needed. The second task of this research is to plan and install several hardwares in a multimedia class room as a digital education platform. The platform includes smart board with touch screen functionality, network server and personal computers. The digital education platform was established as a multimedia class room in the 2nd College of Engineering building, room 16210 by using the Server-Client environment and smart board, personal computer, and internet was connected by a TCP/IP way. For the courseware, hypertext was supported to be web-based, and photo, picture, data and related web links including text were developed in a close relation, it is possible for students to study big amounts of information in a systemized way and to maximize the learning efficiency. The whole range of introductory nuclear engineering course was divided into nuclear fuel cycle, reactor theory, heat transport, and reactor control, and digital contents were developed by each experts, but the final format of the courseware was maintained consistently for easy understanding . Also, the reactor experiment courseware developed by Kyunghee University can be utilized on this platform. 5 refs., 36 figs., 4 tabs. (Author)

  7. Political Aspects of Nuclear Energy Market Development in the Countries of South Asia. NSG Factor in Promoting Nuclear Energy in the Region

    Directory of Open Access Journals (Sweden)

    Boyko Aleksandr Aleksandrovich

    2016-04-01

    Full Text Available South Asian geopolitical face-off of Delhi and Islamabad revealed breaches of the nuclear nonproliferation. This encouraged the greatest nuclear powers to create a mechanism for additional regulation of the nuclear technology and materials export, which is now known as “Nuclear Suppliers’ Group”. This mechanism aims to impose restrictions for the nuclear technology and materials export to the countries that are not members of NPT. These are nuclear programs of India and Pakistan that are pressing challenge on the agenda. India has been a very attractive market for nuclear suppliers, especially the United States, so the restrictions were lifted from Delhi in 2008. However, they remained valid for Pakistan, which wasn’t an appealing market for the American nuclear exporters. As a result, China, which has been a member of NSG since 2004, has initiated building new NPPs in Pakistan getting mixed reaction of the international community. Despite the clearly contradicting Guidelines, the members of NSG haven’t reached common ground on how to restore its supporting role in maintaining the non-proliferation regime. Thus, the Asian nuclear market develops mostly spontaneously, and its future is shaped primarily by the international relations between importers and exporters. Russia isn’t able to influence all the NSG members to change the position, however it can take advantage of the situation for developing nuclear cooperation with the Asian countries to support sustainable development of the South Asian energy market.

  8. Development of Nuclear Engineering Educational Program at Ibaraki University with Regional Collaboration

    Science.gov (United States)

    Matsumura, Kunihito; Kaminaga, Fumito; Kanto, Yasuhiro; Tanaka, Nobuatsu; Saigusa, Mikio; Kikuchi, Kenji; Kurumada, Akira

    The College of Engineering, Ibaraki University is located at the Hitachi city, in the north part of Ibaraki prefecture. Hitachi and Tokai areas are well known as concentration of advanced technology center of nuclear power research organizations. By considering these regional advantages, we developed a new nuclear engineering educational program for students in the Collage of Engineering and The Graduate School of Science and Engineering of Ibaraki University. The program is consisted of the fundamental lectures of nuclear engineering and nuclear engineering experiments. In addition, several observation learning programs by visiting cooperative organizations are also included in the curriculum. In this paper, we report about the progress of the new educational program for nuclear engineering in Ibaraki University.

  9. A review on the status of development in thorium-based nuclear fuels

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Woo; Na, S. H.; Lee, Y. W.; Kim, H. S.; Kim, S. H.; Joung, C.Y

    2000-02-01

    Thorium as an alternative nuclear energy source had been widely investigated in the 1950s-1960s because it is more abundant than uranium, but the studies of thorium nuclear fuel cycle were discontinued by political and economic reasons in the 1970s. Recently, however, renewed interest was vested in thorium-based nuclear fuel cycle because it may generate less long-lived minor actinides and has a lower radiotoxicity of high level wastes after reprocessing compared with the thorium fuel cycle. In this state-of the art report, thorium-based nuclear cycle. In this state-of the art report, thorium-based nuclear fuel cycle and fuel fabrication processes developed so far with different reactor types are reviewed and analyzed to establish basic technologies of thorium fuel fabrication which could meet our situation. (author)

  10. Research and Development Technology Development Roadmaps for the Next Generation Nuclear Plant Project

    Energy Technology Data Exchange (ETDEWEB)

    Ian McKirdy

    2011-07-01

    The U.S. Department of Energy (DOE) has selected the high temperature gas-cooled reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for process heat, hydrogen and electricity production. The reactor will be graphite moderated with helium as the primary coolant and may be either prismatic or pebble-bed. Although, final design features have not yet been determined. Research and Development (R&D) activities are proceeding on those known plant systems to mature the technology, codify the materials for specific applications, and demonstrate the component and system viability in NGNP relevant and integrated environments. Collectively these R&D activities serve to reduce the project risk and enhance the probability of on-budget, on-schedule completion and NRC licensing. As the design progresses, in more detail, toward final design and approval for construction, selected components, which have not been used in a similar application, in a relevant environment nor integrated with other components and systems, must be tested to demonstrate viability at reduced scales and simulations prior to full scale operation. This report and its R&D TDRMs present the path forward and its significance in assuring technical readiness to perform the desired function by: Choreographing the integration between design and R&D activities; and proving selected design components in relevant applications.

  11. Development of an inertial confinement fusion platform to study charged-particle-producing nuclear reactions relevant to nuclear astrophysics

    Science.gov (United States)

    Gatu Johnson, M.; Zylstra, A. B.; Bacher, A.; Brune, C. R.; Casey, D. T.; Forrest, C.; Herrmann, H. W.; Hohenberger, M.; Sayre, D. B.; Bionta, R. M.; Bourgade, J.-L.; Caggiano, J. A.; Cerjan, C.; Craxton, R. S.; Dearborn, D.; Farrell, M.; Frenje, J. A.; Garcia, E. M.; Glebov, V. Yu.; Hale, G.; Hartouni, E. P.; Hatarik, R.; Hohensee, M.; Holunga, D. M.; Hoppe, M.; Janezic, R.; Khan, S. F.; Kilkenny, J. D.; Kim, Y. H.; Knauer, J. P.; Kohut, T. R.; Lahmann, B.; Landoas, O.; Li, C. K.; Marshall, F. J.; Masse, L.; McEvoy, A.; McKenty, P.; McNabb, D. P.; Nikroo, A.; Parham, T. G.; Paris, M.; Petrasso, R. D.; Pino, J.; Radha, P. B.; Remington, B.; Rinderknecht, H. G.; Robey, H.; Rosenberg, M. J.; Rosse, B.; Rubery, M.; Sangster, T. C.; Sanchez, J.; Schmitt, M.; Schoff, M.; Séguin, F. H.; Seka, W.; Sio, H.; Stoeckl, C.; Tipton, R. E.

    2017-04-01

    This paper describes the development of a platform to study astrophysically relevant nuclear reactions using inertial-confinement fusion implosions on the OMEGA and National Ignition Facility laser facilities, with a particular focus on optimizing the implosions to study charged-particle-producing reactions. Primary requirements on the platform are high yield, for high statistics in the fusion product measurements, combined with low areal density, to allow the charged fusion products to escape. This is optimally achieved with direct-drive exploding pusher implosions using thin-glass-shell capsules. Mitigation strategies to eliminate a possible target sheath potential which would accelerate the emitted ions are discussed. The potential impact of kinetic effects on the implosions is also considered. The platform is initially employed to study the complementary T(t,2n)α, T(3He,np)α and 3He(3He,2p)α reactions. Proof-of-principle results from the first experiments demonstrating the ability to accurately measure the energy and yields of charged particles are presented. Lessons learned from these experiments will be used in studies of other reactions. The goals are to explore thermonuclear reaction rates and fundamental nuclear physics in stellar-like plasma environments, and to push this new frontier of nuclear astrophysics into unique regimes not reachable through existing platforms, with thermal ion velocity distributions, plasma screening, and low reactant energies.

  12. Toward the last frontier - A strategy for the evolutionary development of space nuclear power systems

    Science.gov (United States)

    Bennett, Gary L.

    1992-01-01

    A number of exciting mission opportunities are being considered for the 21st century, including advanced robotic science missions to the outer planets and beyond, human exploration of the Moon and Mars, and advanced space transportation systems. All of these missions will require some form of nuclear power; however, it is clear that current budgetary constraints preclude developing many different types of space nuclear power systems. This paper reviews the specific civil space missions which have been identified, the power levels and lifetimes required, and the technologies available. From this an evolutionary space nuclear power program is developed which builds upon the experience of radioisotope thermoelectric generators, dynamic isotope power systems, and space nuclear reactors. It is strongly suggested that not only does this approach make technical and budgetary sense but that it is consistent with the normal development of new technologies.

  13. The socio-political economy of nuclear power development in Japan and South Korea

    Energy Technology Data Exchange (ETDEWEB)

    Valentine, Scott Victor [Graduate School of Public Policy, University of Tokyo, 616 Administration Bureau Building No. 2, 7-3-1 Hongo, Bunkyo-ku, 113-0033 Tokyo (Japan); Sovacool, Benjamin K. [Lee Kuan Yew School of Public Policy, National University of Singapore, 469C Bukit Timah Road, Singapore 259772 (Singapore)

    2010-12-15

    This paper analyzes the socio-cultural, political and economic conditions prevalent during the inception of nuclear power programs in Japan and South Korea in order to identify commonalities which support nuclear power program expansion. The study identifies six factors as having a clear influence on supporting nuclear power development: (1) strong state involvement in guiding economic development; (2) centralization of national energy policymaking and planning; (3) campaigns to link technological progress with national revitalization; (4) influence of technocratic ideology on policy decisions; (5) subordination of challenges to political authority, and (6) low levels of civic activism. The paper postulates that insights from this study can be used to assess the propensity of nations which have the emergent capacity to support nuclear power development to actually embark on such programs. (author)

  14. Development of nuclear energy and radiation textbooks for high school students

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Seung Koo; Park, Pil Han; Choi, Yoon Seok; Kim, Wook; Jeong, Im Soon; Han, Eun Ok [Dept. of Education and Research, Korea Academy of Nuclear Safety, Seoul (Korea, Republic of)

    2015-04-15

    This study aimed to develop textbooks about nuclear energy and radiation targeting high school students-the leaders of the next generation. Students learn about nuclear power generation and radiation through minimal information in science textbooks; most students acquire concepts through teaching-learning activities between teachers and students. Therefore, if a science teacher has an inaccurate perception about nuclear energy and radiation, this may have an improper influence on students. Before the failure of securing social acceptance due to ignorance about nuclear energy and radiation leads to biased political effects, the correct information should be provided in schools to allow future generations to develop educated value judgments. The present textbooks were developed as a part of such effort.

  15. External constraints in Korea`s long-term nuclear development -A search for their resolution-

    Energy Technology Data Exchange (ETDEWEB)

    Yun, Duk Min [IFANS (Korea, Republic of)

    1997-06-01

    Korea`s long-term nuclear development is subject to the external constraints. The most decisive legal constraint is the South-North Joint Declaration of denuclearization in 1991. In order to meet the conditions for the long-term nuclear development, this study proposed and analyzed various policy alternatives to adjust the constraints of the joint declaration. Finally, the long-term approach to the issue, the use of ASIATOM initiative, a strong national commitment to the denuclearization and consolidating cooperation with countries who have adopted nuclear recycle policy were suggested as ideas on how to advance the long-term nuclear research and development under the present situations. (Author) 13 refs., 5 tabs.

  16. Stage-dependent remodeling of the nuclear envelope and lamina during rabbit early embryonic development.

    Science.gov (United States)

    Popken, Jens; Schmid, Volker J; Strauss, Axel; Guengoer, Tuna; Wolf, Eckhard; Zakhartchenko, Valeri

    2016-04-22

    Utilizing 3D structured illumination microscopy, we investigated the quality and quantity of nuclear invaginations and the distribution of nuclear pores during rabbit early embryonic development and identified the exact time point of nucleoporin 153 (NUP153) association with chromatin during mitosis. Contrary to bovine early embryonic nuclei, featuring almost exclusively nuclear invaginations containing a small volume of cytoplasm, nuclei in rabbit early embryonic stages show additionally numerous invaginations containing a large volume of cytoplasm. Small-volume invaginations frequently emanated from large-volume nuclear invaginations but not vice versa, indicating a different underlying mechanism. Large- and small-volume nuclear envelope invaginations required the presence of chromatin, as they were restricted to chromatin-positive areas. The chromatin-free contact areas between nucleolar precursor bodies (NPBs) and large-volume invaginations were free of nuclear pores. Small-volume invaginations were not in contact with NPBs. The number of invaginations and isolated intranuclear vesicles per nucleus peaked at the 4-cell stage. At this stage, the nuclear surface showed highly concentrated clusters of nuclear pores surrounded by areas free of nuclear pores. Isolated intranuclear lamina vesicles were usually NUP153 negative. Cytoplasmic, randomly distributed NUP153-positive clusters were highly abundant at the zygote stage and decreased in number until they were almost absent at the 8-cell stage and later. These large NUP153 clusters may represent a maternally provided NUP153 deposit, but they were not visible as clusters during mitosis. Major genome activation at the 8- to 16-cell stage may mark the switch from a necessity for a deposit to on-demand production. NUP153 association with chromatin is initiated during metaphase before the initiation of the regeneration of the lamina. To our knowledge, the present study demonstrates for the first time major remodeling

  17. The development of regulatory expectations for computer-based safety systems for the UK nuclear programme

    Energy Technology Data Exchange (ETDEWEB)

    Hughes, P. J. [HM Nuclear Installations Inspectorate Marine Engineering Submarines Defence Nuclear Safety Regulator Serco Assurance Redgrave Court, Merton Road, Bootle L20 7HS (United Kingdom); Westwood, R.N; Mark, R. T. [FLEET HQ, Leach Building, Whale Island, Portsmouth, PO2 8BY (United Kingdom); Tapping, K. [Serco Assurance,Thomson House, Risley, Warrington, WA3 6GA (United Kingdom)

    2006-07-01

    The Nuclear Installations Inspectorate (NII) of the UK's Health and Safety Executive (HSE) has completed a review of their Safety Assessment Principles (SAPs) for Nuclear Installations recently. During the period of the SAPs review in 2004-2005 the designers of future UK naval reactor plant were optioneering the control and protection systems that might be implemented. Because there was insufficient regulatory guidance available in the naval sector to support this activity the Defence Nuclear Safety Regulator (DNSR) invited the NII to collaborate with the production of a guidance document that provides clarity of regulatory expectations for the production of safety cases for computer based safety systems. A key part of producing regulatory expectations was identifying the relevant extant standards and sector guidance that reflect good practice. The three principal sources of such good practice were: IAEA Safety Guide NS-G-1.1 (Software for Computer Based Systems Important to Safety in Nuclear Power Plants), European Commission consensus document (Common Position of European Nuclear Regulators for the Licensing of Safety Critical Software for Nuclear Reactors) and IEC nuclear sector standards such as IEC60880. A common understanding has been achieved between the NII and DNSR and regulatory guidance developed which will be used by both NII and DNSR in the assessment of computer-based safety systems and in the further development of more detailed joint technical assessment guidance for both regulatory organisations. (authors)

  18. Development of Improved Burnable Poisons for Commercial Nuclear Power Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Renier, J.A.

    2002-04-17

    Burnable poisons are used in all modern nuclear reactors to permit higher loading of fuel without the necessity of an overly large control rod system. This not only permits a longer core life but can also be used to level the power distribution. Commercial nuclear reactors commonly use B{sub 4}C in separate non-fueled rods and more recently, zirconium boride coatings on the fuel pellets or gadolinium oxide mixed with the fuel. Although the advantages are great, there are problems with using these materials. Boron, which is an effective neutron absorber, transmutes to lithium and helium upon absorption of a neutron. Helium is insoluble and is eventually released to the interior of the fuel rod, where it produces an internal pressure. When sufficiently high, this pressure stress could cause separation of the cladding from the fuel, causing overly high centerline temperatures. Gadolinium has several very strongly absorbing isotopes, but not all have large cross sections and result in residual burnable poison reactivity worth at the end of the fuel life. Even if the amount of this residual absorber is small and the penalty in operation small, the cost of this penalty, even if only several days, can be very high. The objective of this investigation was to study the performance of single isotopes in order to reduce the residual negative reactivity left over at the end of the fuel cycle. Since the behavior of burnable poisons can be strongly influenced by their configuration, four forms for the absorbers were studied: homogeneously mixed with the fuel, mixed with only the outer one-third of the fuel pellet, coated on the perimeter of the fuel pellets, and alloyed with the cladding. In addition, the numbers of fuel rods containing burnable poison were chosen as 8, 16, 64, and 104. Other configurations were chosen for a few special cases. An enrichment of 4.5 wt% {sup 235}U was chosen for most cases for study in order to achieve a 4-year fuel cycle. A standard pressurized

  19. The development of advanced robotics for the nuclear industry -The development of advanced robotic technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jong Min; Lee, Yong Bum; Park, Soon Woong; Cho, Jae Wan; Lee, Nam Ho; Kim, Woong Ki; Moon, Byung Soo; Lee, Young Jae; Kim, Chang Hoi; Kim, Seung Ho; Hwang, Seok Yong; Kim, Byung Soo; Moon, Jae Sun; Lee, Young Kwang; Choi, Kap Joo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-07-01

    The comparison study of 3 kinds of stereo camera modules done in this final year of 4 year`s longterm project shows that regenerating characteristics of stereo image of stereo camera using horizontally moving lens axis method is superior to the other two modules. Base on this comparison result, stereo camera module using horizontally moving lens method is developed. Also, stereo-Boom unit, high definition polarized stereo monitor(KAERI-PSM II) and 10.4sec. auto-stereogram TV using parallax barrier method are developed. These developed systems can be used for people involved in extremely hazardous working area to give vivid reality image of work environment. In the recognition and tracking section, auto-vergencing technology using focus fixation and cepstral filter, stereo camera calibration, range measurement technology using stereo camera module are developed. And active target tracking technology is developed also. In the sensing and intelligent control research part, active radioactivity image monitoring unit is developed. The spatial resolution of monitoring unit is 10cm at 1m distance, FOV is 60x40 deg [HXV], and radioactivity detection limit is 1mR/hr. Also, radiation-resistant inspection camera for nuclear facilities is designed. In the intelligent control section, fuzzy control algorithm for obstacle detouring navigation of mobile robot is developed. The smoothing techniques by fuzzy set is adapted to raise the pliability of obstacle detouring navigation of mobile robot. In order to raise robustness of developed fuzzy algorithm, fuzzy control algorithm is applied to `Truck Backer Upper` problem and tuned. (Abstract Truncated)

  20. International Source Book: Nuclear Fuel Cycle Research and Development Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, K. M.; Lakey, L. T.

    1982-11-01

    This document starts with an overview that summarizes nuclear power policies and waste management activities for nations with significant commercial nuclear fuel cycle activities either under way or planned. A more detailed program summary is then included for each country or international agency conducting nuclear fuel cycle and waste management research and development. This second volume includes the program summaries of those countries listed alphabetically from Japan to Yugoslavia. Information on international agencies and associations, particularly the IAEA, NEA, and CEC, is provided also.

  1. Nuclear Hybrid Energy Systems Initial Integrated Case Study Development and Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Harrison, Thomas J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Greenwood, Michael Scott [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-12-01

    The US Department of Energy Office of Nuclear Energy established the Nuclear Hybrid Energy System (NHES) project to develop a systematic, rigorous, technically accurate set of methods to model, analyze, and optimize the integration of dispatchable nuclear, fossil, and electric storage with an industrial customer. Ideally, the optimized integration of these systems will provide economic and operational benefits to the overall system compared to independent operation, and it will enhance the stability and responsiveness of the grid as intermittent, nondispatchable, renewable resources provide a greater share of grid power.

  2. Development of underwater laser cutting technique for steel and zircaloy for nuclear applications

    Indian Academy of Sciences (India)

    R K Jain; D K Agrawal; S C Vishwakarma; A K Choubey; B N Upadhyaya; S M Oak

    2010-12-01

    In nuclear field, underwater cutting and welding technique is required for post-irradiation examination, maintenance, decommissioning and to reduce storage space of irradiated materials like used zircaloy pressure tubes etc., of nuclear power plants. We have developed underwater cutting technique for 4.2 mm thick zircaloy pressure tubes and up to 6 mm thick steel using fibre-coupled 250 W average power pulsed Nd:YAG laser. This underwater cutting technique will be highly useful in various nuclear applications as well as in dismantling/repair of ship and pipe lines in water.

  3. Development of a utility system for nuclear reaction data file: WinNRDF

    Energy Technology Data Exchange (ETDEWEB)

    Aoyama, Shigeyoshi [Information Processing Center, Kitami Inst. of Tech., Hokkaido (Japan); Ohbayasi, Yosihide; Masui, Hiroshi [Meme Media Lab., Hokkaido Univ., Sapporo (Japan); Chiba, Masaki [Graduate School of Science, Hokkaido Univ., Sapporo (Japan); Kato, Kiyoshi; Ohnishi, Akira [Faculty of Social Information, Sapporo Gakuin Univ., Ebetsu, Hokkaido (Japan)

    2000-03-01

    A utility system, WinNRDF, is developed for charged particle nuclear reaction data of NRDF (Nuclear Reaction Data File) on the Windows interface. By using this system, we can easily search the experimental data of a charged particle nuclear reaction in NRDF than old retrieval systems on the mainframe and also see graphically the experimental data on GUI (Graphical User Interface). We adopted a mechanism of making a new index of keywords to put to practical use of the time dependent properties of the NRDF database. (author)

  4. Cardiac nuclear high mobility group box 1 prevents the development of cardiac hypertrophy and heart failure.

    Science.gov (United States)

    Funayama, Akira; Shishido, Tetsuro; Netsu, Shunsuke; Narumi, Taro; Kadowaki, Shinpei; Takahashi, Hiroki; Miyamoto, Takuya; Watanabe, Tetsu; Woo, Chang-Hoon; Abe, Jun-ichi; Kuwahara, Koichiro; Nakao, Kazuwa; Takeishi, Yasuchika; Kubota, Isao

    2013-09-01

    High mobility group box 1 (HMGB1) is an abundant and ubiquitous nuclear DNA-binding protein that has multiple functions dependent on its cellular location. HMGB1 binds to DNA, facilitating numerous nuclear functions including maintenance of genome stability, transcription, and repair. However, little is known about the effects of nuclear HMGB1 on cardiac hypertrophy and heart failure. The aim of this study was to examine whether nuclear HMGB1 plays a role in the development of cardiac hypertrophy induced by pressure overload. Analysis of human biopsy samples by immunohistochemistry showed decreased nuclear HMGB1 expression in failing hearts compared with normal hearts. Nuclear HMGB1 decreased in response to both endothelin-1 (ET-1) and angiotensin II (Ang II) stimulation in neonatal rat cardiomyocytes, where nuclear HMGB1 was acetylated and translocated to the cytoplasm. Overexpression of nuclear HMGB1 attenuated ET-1 induced cardiomyocyte hypertrophy. Thoracic transverse aortic constriction (TAC) was performed in transgenic mice with cardiac-specific overexpression of HMGB1 (HMGB1-Tg) and wild-type (WT) mice. Cardiac hypertrophy after TAC was attenuated in HMGB1-Tg mice and the survival rate after TAC was higher in HMGB1-Tg mice than in WT mice. Induction of foetal cardiac genes was decreased in HMGB1-Tg mice compared with WT mice. Nuclear HMGB1 expression was preserved in HMGB1-Tg mice compared with WT mice and significantly attenuated DNA damage after TAC was attenuated in HMGB1-TG mice. These results suggest that the maintenance of stable nuclear HMGB1 levels prevents hypertrophy and heart failure by inhibiting DNA damage.

  5. Principles of designing mobile robots for nuclear applications: Some Soviet development projects

    Energy Technology Data Exchange (ETDEWEB)

    Adamov, E.O.; Ivanov, V.G.; Meieran, H.B.

    1990-01-01

    The I.V. Kurchatov Institute of Atomic Energy and the Research and Design Institute of Power Engineering, both designers of nuclear power plant systems and located in Moscow, USSR, have collectively recognized the positive merits of utilizing mobile robots in the nuclear industry. They have given authority to their subsidiary agency CENOTECH to mount an active campaign to program the development of new generations of mobile robots that will support routine and emergency situation operations in the nuclear industry. CENOTECH's rationale for design and performance requirements of mobile robot units to be utilized in the nuclear industry is presented in this paper. A description of design, performance requirements, and operational characteristics of four mobile robots that have been developed at CENOTECH within the past 3 yr is also presented: the 2-tracked KURSOR ; the 4 hybrid-wheeled TELER; the 12-wheeled BUGGY with articulated platforms; and the 2-tracked SADKO.

  6. Nuclear safeguards research and development program. Status report, January--April 1977

    Energy Technology Data Exchange (ETDEWEB)

    Sapir, J.L. (comp.)

    1977-06-01

    The status of the Nuclear Safeguards Research and Development program pursued by LASL Safeguards Groups Q-1, Q-2, Q-3, and Q-4 is presented . Topics covered include nondestructive assay technology development and applications, international safeguards, perimeter safeguards and surveillance, concepts and subsystems development (e.g., DYMAC program), integrated safeguards systems, training courses, and technology transfer.

  7. Effects of Nuclear Energy on Sustainable Development and Energy Security: Sodium-Cooled Fast Reactor Case

    OpenAIRE

    Sungjoo Lee; Byungun Yoon; Juneseuk Shin

    2016-01-01

    We propose a stepwise method of selecting appropriate indicators to measure effects of a specific nuclear energy option on sustainable development and energy security, and also to compare an energy option with another. Focusing on the sodium-cooled fast reactor, one of the highlighted Generation IV reactors, we measure and compare its effects with the standard pressurized water reactor-based nuclear power, and then with coal power. Collecting 36 indicators, five experts select seven key indic...

  8. Proceedings of the sixth annual conference of the International Nuclear Target Development Society

    Energy Technology Data Exchange (ETDEWEB)

    Steers, G. (comp.)

    1978-08-01

    The Sixth Annual Conference of the International Nuclear Target Development Society was held at the Lawrence Berkeley Laboratory, University of California, Berkeley, California, on October 19--21, 1977. The discussion covered nuclear target preparation by evaporation, reduction of oxides, electrodeposition, reactive sputtering, rolling, gas jets, and related techniques. Abstracts were prepared for eighteen of the papers presented at the conference and are included in the data base. (GHT)

  9. Development of a utility system for charged particle nuclear reaction data by using intelligentPad

    Energy Technology Data Exchange (ETDEWEB)

    Aoyama, Shigeyoshi; Ohbayashi, Yoshihide [Information Processing Center, Kitami Institute of Technology, Kitami, Hokkaido (Japan); Masui, Hiroshi [Meme Media Laboratory, Hokkaido University, Sapporo, Hokkaido (Japan); Kato, Kiyoshi [Hokkaido University, Graduate School of Science, Sapporo, Hokkaido (Japan); Chiba, Masaki [Faculty of Social Information, Sapporo Gakuin Univ., Ebetsu, Hokkaido (Japan)

    2000-03-01

    We have developed a utility system, WinNRDF2, for a nuclear charged particle reaction data of NRDF (Nuclear Reaction Data File) on the IntelligentPad architecture. By using the system, we can search the experimental data of a charged particle reaction of NRDF. Furthermore, we also see the experimental data by using graphic pads which was made through the CONTIP project. (author)

  10. Management of communication area in a nuclear research and development institute

    Energy Technology Data Exchange (ETDEWEB)

    Soares, Wellington Antonio [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil). Servico de Negocios e Comunicacao]. E-mail: soaresw@cdtn.br

    2005-07-01

    Nuclear energy to the general public is always associated to the production of nuclear weapons or to nuclear and radiological accidents. Public communication actions done by the National Commission of Nuclear Energy (CNEN) have been contributing to make known the social and peaceful applications of nuclear energy, reaching different kinds of public. Interaction programs with society and in particular with students have also been carried out by the Nuclear Technology Development Center (CDTN/CNEN). Measuring public communication results can help to show that financial resource in this area should be considered as investment and not as expenses. One needs therefore a well-established managing system. Fundamentals of the National Quality Award Criteria for Excellence - PNQ are being applied in the area in charge of business and public communication at CDTN. Systematic registration of results started in 2000 and a gradual increase in the number of means of communication for the internal public has occurred in the last five years. The Center has now a bimonthly newspaper edition. Communication indicators have shown an increasing number of students received in the Center or provided with lectures in schools. Results of satisfaction inquiry from these students show good results. The implemented management system has allowed informing the nature and quantity of people reached by the information on nuclear applications and the improvement in the institutional image. (author)

  11. Assessing the need for nuclear cardiology and other advanced cardiac imaging modalities in the developing world.

    Science.gov (United States)

    Vitola, João V; Shaw, Leslee J; Allam, Adel H; Orellana, Pilar; Peix, Amalia; Ellmann, Annare; Allman, Kevin C; Lee, B N; Siritara, Chanika; Keng, Felix Y J; Sambuceti, Gianmario; Kiess, Marla C; Giubbini, Raffaele; Bouyoucef, Salaheddine E; He, Zuo-Xiang; Thomas, Gregory S; Mut, Fernando; Dondi, Maurizio

    2009-01-01

    In 2005, 80% of cardiovascular disease (CVD) deaths occurred in low- to middle-income countries (i.e., developing nations). Cardiovascular imaging, such as myocardial perfusion SPECT, is one method that may be applied to detect and foster improved detection of at-risk patients. This document will review the availability and utilization for nuclear cardiology procedures worldwide and propose strategies to devise regional centers of excellence to achieve quality imaging around the world. As a means to establish the current state of nuclear cardiology, International Atomic Energy Agency member and non-member states were queried as to annual utilization of nuclear cardiology procedures. Other sources for imaging statistics included data from medical societies (American Society of Nuclear Cardiology, European Society of Cardiology, and the European Association of Nuclear Medicine) and nuclear cardiology working groups within several nations. Utilization was calculated by dividing annual procedural volume by 2007 population statistics (/100,000) and categorized as high (>1,000/100,000), moderate-high (250-999/100,000), moderate (100-249/100,000), low-moderate (50-99/100,000) and low (Algeria and Egypt); perhaps the result of accessible high-quality training programs. Worldwide utilization patterns for nuclear cardiology vary substantially and may be influenced by physician access to training and education programs. Development of regional training centers of excellence can guide utilization of nuclear cardiology through the application of guideline- and appropriateness-driven testing, training, continuing education, and quality assurance programs aiding developing nations to confront the epidemics of CVD.

  12. 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

    Using a vertical education enhancement model, a Nuclear Education and Research Vertical Enhancement (NERVE) program was developed. The NERVE program is aimed at developing nuclear engineering education and research to 1) enhance skilled workforce development in disciplines relevant to nuclear power, national security and medical physics, and 2) increase the number of students and faculty from underrepresented groups (women and minorities) in fields related to the nuclear industry. The program uses multi-track training activities that vertically cut across the several education domains: undergraduate degree programs, graduate schools, and post-doctoral training. In this paper, we present the results of an integrative curriculum development in the NERVE program. The curriculum development began with nuclear content infusion into existing science, engineering and technology courses. The second step involved the development of nuclear engineering courses: 1) Introduction to Nuclear Engineering, 2) Nuclear Engineering I, and 2) Nuclear Engineering II. The third step is the establishment of nuclear engineering concentrations in two engineering degree programs: 1) electrical engineering, and 2) mechanical engineering. A major outcome of the NERVE program is a collaborative infrastructure that uses laboratory work, internships at nuclear facilities, on-campus research, and mentoring in collaboration with industry and government partners to provide hands-on training for students. The major activities of the research and education collaborations include: - One-week spring training workshop at Brookhaven National Laboratory: The one-week training and workshop is used to enhance research collaborations and train faculty and students on user facilities/equipment at Brookhaven National Laboratory, and for summer research internships. Participants included students, faculty members at Alabama A and M University and research collaborators at BNL. The activities include 1) tour and

  13. Challenges in developing human resources for nuclear safety in South Africa

    Energy Technology Data Exchange (ETDEWEB)

    Tsatsi, Louisa [National Nuclear Regulator, PO BOX 7106, 00046 Centurion (South Africa)

    2008-07-01

    Challenges in developing Human Resources for nuclear safety in South Africa ESKOM Holding Limited which is the South African Government owned utility, operates over 10 power stations. The total installed is about 40 GW, and nuclear contributes only 6 percent. The existing nuclear power station, Koeberg NPP, is comprised of two 900 MW(e) units at the South African west coast near Cape Town. The South African Government has a policy to increase the share of nuclear in the generation mix from 6 percent to 15 percent before the year 2020. The challenge is that there have been a 'greying' of nuclear experts and a shrinking of nuclear engineering and science departments. As a consequence of this, ESKOM has realized that a large number of young engineers and scientists would have to be recruited and then trained in South Africa and abroad. Some people, especially high performers in the industry are continually looking for new challenges and opportunities and though it is important in the nuclear industry to retain these key staff members it have proved to be a serious challenge. The nuclear industry had to consider their national training infrastructures and the South African government in partnership with ESKOM, NECSA and PBMR has started a process of funding university chairs in reactor engineering and allied subjects. These departments undertake research and provide training for the South African nuclear industry. The recruitment process has initially involved the transfer of personnel from ESKOM, NECSA as well as direct recruitment from the market. The primary recruitment process going forward will be from universities and other Further Education Training (FET) institutions with a focus on ESKOM and PBMR providing the specific nuclear training. In this regard, both ESKOM and PBMR provide bursaries, project work and other assistance to selected candidates. Upon completion of studies, the specific training is provided both in-house and with partner national

  14. Present status and needs of human resource development in the nuclear field in the Philippines

    Energy Technology Data Exchange (ETDEWEB)

    Bernido, Corazon C.; Roceles, Pilar C. [Philippine Nuclear Research Institute, Commonwealth Avenue, Diliman, Quezon (Philippines)

    2000-12-01

    The first nuclear power plant was nearing completion. However, due to change in political climate and support for the nuclear power program, this has been mothballed. There is a possibility for the introduction of nuclear power plant in the country's projected energy sources by the year 2020. The country has one research reactor, but at the present time it is undergoing repair and is not operational. The Philippine Nuclear Research Institute (PNRI), an Institute under the Department of Science and Technology (DOST), is the sole government agency mandated by the law to take charge of all matters pertaining to nuclear science and technology, and the regulation of nuclear energy. There is one another government agency, the Radiation Health Service (RHS) of the Department of Health, which is responsible for regulating the use and application of X-rays and non-ionizing radiation. The PNRI conducts national training courses in nuclear science and technology, and radiation protection to users of radioisotopes. Individual courses are outlined in the paper. Up to the present time, around 7,300 have participated in national training courses conducted by PNRI. Distributions of PNRI trainees are: 53 % for industrial, 12 % medical, 12 % for academe, and 23 % for others. Nuclear science and technology education in schools and universities are presented. The International Atomic Energy Agency (IAEA) training activities availed 77 % of the total foreign training from 1993 to 1998; Japan follows next at 20 %; and others comprise the remaining 3 %. An approach to training and human resources development, which could reach out to more target trainees, is Distance Learning. In 1998, as a part of a Regional Cooperative Agreement (RCA) and IAEA project, the Philippines participated in the trial of distance learning modules in radiation protection. The distance learning modules were developed at the Australian Nuclear Science and Technology Organization (ANSTO). These modules will

  15. 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.

  16. Concept of development of nuclear power based on LMFBR operation in open nuclear fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Toshinsky, G.I. [Inst. of Physics and Power Engineering, Obninsk (Russian Federation)

    1996-08-01

    The preliminary assessments performed show that it is reasonable to investigate in the future the possibilities of FBR efficient operation with the open NFC. To improve its safety it is expedient to use the lead-bismuth alloy as a coolant. In order to operate with depleted uranium make-up it is necessary to meet a number of requirements providing the reactor criticality due to plutonium build-up and BR > 1. These requirements are as follows: a large core (20--25 m{sup 3}); a high fuel volume fraction (> 60%); utilization of dense metallic fuel; a high fuel burn-up--at a level of 20% of h.a. Making use of these reactors should allow the NP fuel base to be extended more than 10 times without making NFC closed. It provides improving NP safety during a sufficiently long stage of its development.

  17. The development of radiation hardened robot for nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seung Ho; Jung, Seung Ho; Kim, Byung Soo and others

    2000-04-01

    The work conducted in this stage covers development of core technology of tele-robot system including monitoring technique in high-level radioactive area, tele-sensing technology and radiation-hardened technology for the non-destructive tele-inspection system which monitors the primary coolant system during the normal operations of PHWR(Pressurized Heavy Water Reactor) NPPs and measures the decrease of bending part of feeder pipe during overall. Based on the developed core technology, the monitoring mobile robot system of the primary coolant system and the feeder pipe inspecting robot system are developed.

  18. A study on the internal and international environment for nuclear research and development

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Keun Bae; Choi, Y. M.; Lee, K. S.; Lee, B. W.; Ko, H. S

    1997-06-01

    It is essential for Korea to enlarge nuclear energy utilization and development and to develop nuclear fuel cycle technology. However some domestic and international restraints are existing to achieve above goals. Therefore, the consideration for the environmental prospect of nuclear energy development is needed to solve those restraints. The current North Korea`s policies and future relations between two countries in Korean peninsular in respect to domestic restraints are examined and forecasted in Chapter 2. This analysis tries to develop new approaches to solve internal and external major problems through forecasting the future on nuclear nonproliferation policy of U. S. An in-depth study on resolving international and inter-Korean restrictions in political and strategic perspectives is carried out in Chapter 3. The various policy alternatives to adjust the constraints of the joint declaration are proposed and analysed in Chapter. It contains also the national commitments that are suggested as ideas on how to advance the long-term nuclear research and development under the present situation. (author). 100 refs.

  19. The Defense Threat Reduction Agency's Technical Nuclear Forensics Research and Development Program

    Science.gov (United States)

    Franks, J.

    2015-12-01

    The Defense Threat Reduction Agency (DTRA) Technical Nuclear Forensics (TNF) Research and Development (R&D) Program's overarching goal is to design, develop, demonstrate, and transition advanced technologies and methodologies that improve the interagency operational capability to provide forensics conclusions after the detonation of a nuclear device. This goal is attained through the execution of three focus areas covering the span of the TNF process to enable strategic decision-making (attribution): Nuclear Forensic Materials Exploitation - Development of targeted technologies, methodologies and tools enabling the timely collection, analysis and interpretation of detonation materials.Prompt Nuclear Effects Exploitation - Improve ground-based capabilities to collect prompt nuclear device outputs and effects data for rapid, complementary and corroborative information.Nuclear Forensics Device Characterization - Development of a validated and verified capability to reverse model a nuclear device with high confidence from observables (e.g., prompt diagnostics, sample analysis, etc.) seen after an attack. This presentation will outline DTRA's TNF R&D strategy and current investments, with efforts focusing on: (1) introducing new technical data collection capabilities (e.g., ground-based prompt diagnostics sensor systems; innovative debris collection and analysis); (2) developing new TNF process paradigms and concepts of operations to decrease timelines and uncertainties, and increase results confidence; (3) enhanced validation and verification (V&V) of capabilities through technology evaluations and demonstrations; and (4) updated weapon output predictions to account for the modern threat environment. A key challenge to expanding these efforts to a global capability is the need for increased post-detonation TNF international cooperation, collaboration and peer reviews.

  20. Changes in Nuclear Orientation Patterns of Chromosome 11 during Mouse Plasmacytoma Development

    Directory of Open Access Journals (Sweden)

    Ann-Kristin Schmälter

    2015-10-01

    Full Text Available Studying changes in nuclear architecture is a unique approach toward the understanding of nuclear remodeling during tumor development. One aspect of nuclear architecture is the orientation of chromosomes in the three-dimensional nuclear space. We studied mouse chromosome 11 in lymphocytes of [T38HxBALB/c]N mice with a reciprocal translocation between chromosome X and 11 (T38HT(X;11 exhibiting a long chromosome T(11;X and a short chromosome T(X;11 and in fast-onset plasmacytomas (PCTs induced in the same strain. We determined the three-dimensional orientation of chromosome 11 using a mouse chromosome 11 specific multicolor banding probe. We also examined the nuclear position of the small translocation chromosome T(X;11 which contains cytoband 11E2 and parts of E1. Chromosomes can point either with their centromeric or with their telomeric end toward the nuclear center or periphery, or their position is found in parallel to the nuclear border. In T38HT(X;11 nuclei, the most frequently observed orientation pattern was with both chromosomes 11 in parallel to the nuclear border (“PP”. PCT cells showed nuclei with two or more copies of chromosome 11. In PCTs, the most frequent orientation pattern was with one chromosome in parallel and the other pointing with its centromeric end toward the nuclear periphery (“CP”. There is a significant difference between the orientation patterns observed in T38HT(X;11 and in PCT nuclei (P < .0001.

  1. Moldova Power Sources Development including Nuclear Power Plant possible participation

    Directory of Open Access Journals (Sweden)

    Comendant

    2007-12-01

    Full Text Available For the new power market conditions Moldova power sources development options up to 2030 are evaluated, attempting to propose the best solutions in this respect and the ways they be realized.

  2. Effects of Nuclear Energy on Sustainable Development and Energy Security: Sodium-Cooled Fast Reactor Case

    Directory of Open Access Journals (Sweden)

    Sungjoo Lee

    2016-09-01

    Full Text Available We propose a stepwise method of selecting appropriate indicators to measure effects of a specific nuclear energy option on sustainable development and energy security, and also to compare an energy option with another. Focusing on the sodium-cooled fast reactor, one of the highlighted Generation IV reactors, we measure and compare its effects with the standard pressurized water reactor-based nuclear power, and then with coal power. Collecting 36 indicators, five experts select seven key indicators to meet data availability, nuclear energy relevancy, comparability among energy options, and fit with Korean energy policy objectives. The results show that sodium-cooled fast reactors is a better alternative than existing nuclear power as well as coal electricity generation across social, economic and environmental dimensions. Our method makes comparison between energy alternatives easier, thereby clarifying consequences of different energy policy decisions.

  3. Accidental safety analysis methodology development in decommission of the nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Park, G. H.; Hwang, J. H.; Jae, M. S.; Seong, J. H.; Shin, S. H.; Cheong, S. J.; Pae, J. H.; Ang, G. R.; Lee, J. U. [Seoul National Univ., Seoul (Korea, Republic of)

    2002-03-15

    Decontamination and Decommissioning (D and D) of a nuclear reactor cost about 20% of construction expense and production of nuclear wastes during decommissioning makes environmental issues. Decommissioning of a nuclear reactor in Korea is in a just beginning stage, lacking clear standards and regulations for decommissioning. This work accident safety analysis in decommissioning of the nuclear facility can be a solid ground for the standards and regulations. For source term analysis for Kori-1 reactor vessel, MCNP/ORIGEN calculation methodology was applied. The activity of each important nuclide in the vessel was estimated at a time after 2008, the year Kori-1 plant is supposed to be decommissioned. And a methodology for risk analysis assessment in decommissioning was developed.

  4. Development of Operation of Nuclear Technology Education Program for Mutual Technical Cooperation

    Energy Technology Data Exchange (ETDEWEB)

    Lee, H. Y.; Han, K. W.; Lee, E. J. (and others)

    2004-12-15

    The objective of this project is to provide training opportunities to key personnel from developing countries in the field of nuclear technologies through which it would be possible to expand our nation's role as a technology donor and as a leading country in the international nuclear society. In addition, it is expected that this training course would be useful for building a foundation to enter the international markets of nuclear technology and related products. Through this project, it was possible to obtain the current status of the nuclear industries in the countries with which potential cooperation would be expected in the future. Inviting key manager groups from countries which are interested in technology transfer from other countries could provide them with an opportunity to experience our nation's nuclear industries and technologies. Specifically, this project could open with a seminar in Kazakhstan which has abundant natural resources including uranium. Through this visit, it was possible to enhance the cooperation between the two countries in nuclear technology, and it opened a way to cooperate in the support of the Kazakhstan medical radioisotope center and human resources development.

  5. An Overview of Facilities and Capabilities to Support the Development of Nuclear Thermal Propulsion

    Energy Technology Data Exchange (ETDEWEB)

    James Werner; Sam Bhattacharyya; Mike Houts

    2011-02-01

    Abstract. The future of American space exploration depends on the ability to rapidly and economically access locations of interest throughout the solar system. There is a large body of work (both in the US and the Former Soviet Union) that show that Nuclear Thermal Propulsion (NTP) is the most technically mature, advanced propulsion system that can enable this rapid and economical access by its ability to provide a step increase above what is a feasible using a traditional chemical rocket system. For an NTP system to be deployed, the earlier measurements and recent predictions of the performance of the fuel and the reactor system need to be confirmed experimentally prior to launch. Major fuel and reactor system issues to be addressed include fuel performance at temperature, hydrogen compatibility, fission product retention, and restart capability. The prime issue to be addressed for reactor system performance testing involves finding an affordable and environmentally acceptable method to test a range of engine sizes using a combination of nuclear and non-nuclear test facilities. This paper provides an assessment of some of the capabilities and facilities that are available or will be needed to develop and test the nuclear fuel, and reactor components. It will also address briefly options to take advantage of the greatly improvement in computation/simulation and materials processing capabilities that would contribute to making the development of an NTP system more affordable. Keywords: Nuclear Thermal Propulsion (NTP), Fuel fabrication, nuclear testing, test facilities.

  6. Cooperation of nuclear manpower development between Viet Nam and Korea in order to enhance establishment of infrastructure in exporting nuclear technology to Viet Nam

    Energy Technology Data Exchange (ETDEWEB)

    Lee, E. J.; Han, K. W.; Park, J. K.; Kim, Y. T.; Nam, Y. M.; Jang, Y. H.; Yang, M. H

    2003-08-15

    Through this project, KAERI provided OJT Programme to 3 nuclear experts of Viet Nam at the KAERI for 3 months as a cooperation of human resource development in the field of nuclear policy, nuclear safety analysis and thermo hydraulic. We could have publicity activities of S/W and H/W then achieve an advantage position of economical and technical in exporting nuclear technology to Viet Nam. Also we have provided a training course and seminar for a high-level delegation of nuclear policy decision makers, which is consisted of 5 deputy ministers and general directors of Viet Nam in Korea. Thus we could have Vietnamese who are favoring Korea. The KAERI will also prepare a data base of trained Vietnamese in Korea for the maximum utilization of them in cooperating with Viet Nam. We accomplished the cooperation of human resource development and providing program and curriculum of the nuclear education and training in Viet Nam. Furthermore, it is expected that the enhancement of nuclear technical cooperation between Viet Nam and Korea and the nuclear human resource development.

  7. The development of a neuroscience-based methodology for the nuclear energy learning/teaching process

    Energy Technology Data Exchange (ETDEWEB)

    Barabas, Roberta de C.; Sabundjian, Gaiane, E-mail: robertabarabas@usp.br, E-mail: gdjian@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    When compared to other energy sources such as fossil fuels, coal, oil, and gas, nuclear energy has perhaps the lowest impact on the environment. Moreover, nuclear energy has also benefited other fields such as medicine, pharmaceutical industry, and agriculture, among others. However, despite all benefits that result from the peaceful uses of nuclear energy, the theme is still addressed with prejudice. Education may be the starting point for public acceptance of nuclear energy as it provides pedagogical approaches, learning environments, and human resources, which are essential conditions for effective learning. So far nuclear energy educational researches have been conducted using only conventional assessment methods. The global educational scenario has demonstrated absence of neuroscience-based methods for the teaching of nuclear energy, and that may be an opportunity for developing new strategic teaching methods that will help demystifying the theme consequently improving public acceptance of this type of energy. This work aims to present the first step of a methodology in progress based on researches in neuroscience to be applied to Brazilian science teachers in order to contribute to an effective teaching/learning process. This research will use the Implicit Association Test (IAT) to verify implicit attitudes of science teachers concerning nuclear energy. Results will provide data for the next steps of the research. The literature has not reported a similar neuroscience-based methodology applied to the nuclear energy learning/teaching process; therefore, this has demonstrated to be an innovating methodology. The development of the methodology is in progress and the results will be presented in future works. (author)

  8. Development of a nuclear morphometric signature for prostate cancer risk in negative biopsies.

    Directory of Open Access Journals (Sweden)

    Peter H Gann

    Full Text Available BACKGROUND: Our objective was to develop and validate a multi-feature nuclear score based on image analysis of direct DNA staining, and to test its association with field effects and subsequent detection of prostate cancer (PCa in benign biopsies. METHODS: Tissue sections from 39 prostatectomies were Feulgen-stained and digitally scanned (400×, providing maps of DNA content per pixel. PCa and benign epithelial nuclei were randomly selected for measurement of 52 basic morphometric features. Logistic regression models discriminating benign from PCa nuclei, and benign from malignant nuclear populations, were built and cross-validated by AUC analysis. Nuclear populations were randomly collected 5 mm from cancer foci, and from cancer-free prostates, HGPIN, and PCa Gleason grade 3-5. Nuclei also were collected from negative biopsy subjects who had a subsequent diagnosis of PCa and age-matched cancer-free controls (20 pairs. RESULTS: A multi-feature nuclear score discriminated cancer from benign cell populations with AUCs of 0.91 and 0.79, respectively, in training and validation sets of patients. In prostatectomy samples, both nuclear- and population-level models revealed cancer-like features in benign nuclei adjacent to PCa, compared to nuclei that were more distant or from PCa-free glands. In negative biopsies, a validated model with 5 variance features yielded significantly higher scores in cases than controls (P = 0.026. CONCLUSIONS: A multifeature nuclear morphometric score, obtained by automated digital analysis, was validated for discrimination of benign from cancer nuclei. This score demonstrated field effects in benign epithelial nuclei at varying distance from PCa lesions, and was associated with subsequent PCa detection in negative biopsies. IMPACT: This nuclear score shows promise as a risk predictor among men with negative biopsies and as an intermediate biomarker in Phase II chemoprevention trials. The results also suggest that

  9. Historical evolution of nuclear energy systems development and related activities in JAERI. Fission, fusion, accelerator utilization

    Energy Technology Data Exchange (ETDEWEB)

    Tone, Tatsuzo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    Overview of the historical evolution of nuclear energy systems development and related activities in JAERI is given in the report. This report reviews the research and development for light water reactor, fast breeder reactor, high temperature gas reactor, fusion reactor and utilization of accelerator-based neutron source. (author)

  10. Development of atomic-beam resonance method to measure the nuclear moments of unstable nuclei

    Energy Technology Data Exchange (ETDEWEB)

    Sugimoto, T., E-mail: sugimoto@ribf.riken.jp [SPring-8 (Japan); Asahi, K. [Tokyo Institute of Technology, Department of Physics (Japan); Kawamura, H.; Murata, J. [Rikkyo University, Department of Physics (Japan); Nagae, D.; Shimada, K. [Tokyo Institute of Technology, Department of Physics (Japan); Ueno, H.; Yoshimi, A. [RIKEN Nishina Center (Japan)

    2008-01-15

    We have been working on the development of a new technique of atomic-beam resonance method to measure the nuclear moments of unstable nuclei. In the present study, an ion-guiding system to be used as an atomic-beam source have been developed.

  11. Antecedents and perspectives on the development of nuclear energy in Chile

    Science.gov (United States)

    Gutiérrez, Gonzalo

    2014-05-01

    A review of activities and future prospects of nuclear energy in Chile is presented. It shows that the development of this sector is closely linked to the history of the Chilean Nuclear Energy Commission, CCHEN, established in 1965. We can distinguish three stages in its development: the installation, culminating at the beginning of 1974 with the La Reina experimental nuclear reactor went critical. Then a phase of consolidation, which reduces the activity of scientific research and stresses the application, between the years 1974 and the end of the eighties, and finally the last twenty years, a stage of continuity marked by a loss of importance and leadership of the institution at the national level, despite having important specific initiatives in the 2000s, such as the successful development of fuel elements, the installation of a cyclotron that allows the execution of PET diagnosis for the first time in the country and the consolidation of a research laboratory on plasma and nuclear fusion. At present there is a consensus that nuclear sector in Chile needs to be placed in accordance with the development experienced by the country, and therefore requires a profound restructuring of the CCHEN, reviewing its vision, mission and work program. Here is a proposal in this regard.

  12. 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.

  13. Dynamics of nuclear matrix proteome during embryonic development in Drosophila melanogaster

    Indian Academy of Sciences (India)

    Parul Varma; Rakesh K Mishra

    2011-08-01

    Embryonic development is a complex and dynamic process that involves spatiotemporal expression of genes in a highly coordinated manner. Multiple levels of nuclear architecture maintain the fidelity of gene expression programme. One of the components of nuclear architecture, which is believed to play an important role in regulation of gene expression, is the nuclear matrix (NuMat). Many studies over the past few years have tried to analyse the components of this non-chromatin scaffolding of the nucleus and have provided evidences of its structural and functional complexity. However, the relationship of NuMat with the process of embryonic development still remains poorly understood. Here, we report a comparative analysis of the NuMat proteomes of early and late stage Drosophila melanogaster embryos and show that 65% of the NuMat proteome is dynamic during development. Our study establishes links between the dynamics of nuclear architecture and embryonic development and provides tools to further understand the process such as cellular differentiation in the context of higher-order nuclear organization.

  14. Development of New Drummed Nuclear Waste Neutron Counting System

    Institute of Scientific and Technical Information of China (English)

    ZHU; Li-qun; XU; Xiao-ming; BAI; Lei; LI; Xin-jun; GU; Shao-gang; HE; Li-xia; WANG; Mian

    2012-01-01

    <正>The development of a new neutron counting system (Fig. 1) for 200 L drummed radioactive waste measurement has been accomplished in this year. This waste neutron counting system is mainly used for solid radioactive waste classification. It is based on the passive neutron counting technique. The amount of radionuclide contained in the waste is

  15. Development of new business opportunities for minorities in nuclear energy. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Spight, C.

    1980-12-15

    In Part I of this report the basis for the optimal development of new business opportunities for minorities in nuclear energy programs is defined within the successful completion of all contract tasks. The basis presented consists of an identification of a set of qualified minority-owned small businesses, a defined reservoir of highly trained minorities with applicable expertise, a policy context for the development of opportunities, and a proposed networking structure for information transfer/professional development. In Part II a contractor-focused analysis of the structure of the nuclear industry, a breakdown of the DOE nuclear program by region and functional area, and a directory of minority-owned small businesses by region are presented.

  16. Development of a Nuclear Plant Analyzer for Education and Operation Guide of the CANDU Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Suk, Su Dong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Oh, S. K.; Kim, H. D.; Cho, U. Y.; Lim, J. C.; Kim, S. B.; Kim, H. J.; Park, J. W.; Yeom, C. S.; Suh, J. S.; Park, K. S.; Jung, J. B.; Lee, K. M.; Ahn, H. J.; Lee, I. K. [Institute for Advanced Engineering, Yongin (Korea, Republic of)

    1997-09-01

    Operator training through the utilization of the NPA can improve efficiently the operator`s capability to cope with plant abnormal behaviors and enhance the safety and operability of nuclear power plants (NPP). Recent trend toward the computing automation and integrated design approach in NPP design analysis recognizes importance of the utilization of NPA technology. Major efforts are made into the expansion of functional capability of the CANDU plant simulation/analysis program obtained through the previous CANDU engineering R and D activities at IAE and into the development of configuration design technology for visualization through graphic display network. Through the simulation tests on the predictive capability of the plant simulation/analysis program and the examination of behavior of the plant operation parameters in typical operational and upset transients, the validation and improvement of the models for the major plant systems have been made. The reactor kinetics model has been improved for 3-D neutronic transient problems. Reactor burnup calculation and on-power fuelling capability have been modelled for the CANDU in-core fuel management practice. Furthermore, the graphic display of simulation results and control panels is user-interactively visualized, and the establishment of basic distributed computing network system through server/client concept with multimedia technique are tried for real time simulation and computational efficiency. The present simulation program has a limitation on the analysis for fast transient problems because of the lack of the explicit two-phase flow model, however, a CANDU NPA which has been developed as the mid-term part of our long term goal constructing `Simulation Based CANDU Design and Analysis System` is anticipated to be used as an assistant tool for nuclear system engineers and plant operators, and as a basic tool for the development of an advanced integrated engineering analyzer. 29 refs., 9 tabs., 110 figs

  17. The state of the art report on the development of advanced nuclear fuel cladding tube

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jeong Yong; Jeong, Yong Hwan; Park, Sang Yoon; Lee, Myung Ho; Baek, Jong Hyuk; Nam, Cheol; Choi, Byung Kwon

    2001-04-01

    Since the operating conditions of modern PWR trend toward long-term operation, high burn-up, high coolant temperature and high pH, the need to develop a new advanced nuclear fuel cladding as an alternative to Zircaloy-4 increased. To overcome this problem, a number of researches to develop a advanced nuclear fuel cladding tube with superior corrosion resistance and creep resistance have been performed in many advanced nations in the field of nuclear power. Especially, some advanced cladding tubes are already confirmed to have an excellent in-pile properties from the test results in commercial reactor. Also in Korea, KAERI has been researching extensively to develop a high burn-up nuclear fuel cladding Zr alloy since 1990. To design new alloys, it is necessary to study the state of the art on the development of advanced alloys in other countries. In this report, as a part of development of advanced Zr alloy, we studied the state of the art on the development of ZIRLO in U.S.A., E635 in Russia, M5 in France, and MDA and NDA in Japan, which will be applied as basic data to develop an advanced Zr alloy.

  18. Basic Research and Development Effort to Design a Micro Nuclear Power Plant for Brazilian Space Applications

    Science.gov (United States)

    Guimares, L. N. F.; Camillo, G. P.; Placco, G. M.; Barrios, G., A., Jr.; Do Nascimento, J. A.; Borges, E. M.; De Castro Lobo, P. D.

    For some years the Nuclear Energy Division of the Institute for Advanced Studies is conducting the TERRA (Portuguese abbreviation for advanced fast reactor technology) project. This project aims at research and development of the key issues related with nuclear energy applied to space technology. The purpose of this development is to allow future Brazilian space explorers the access of a good and reliable heat, power and/or propulsion system based on nuclear energy. Efforts are being made in fuel and nuclear core design, designing and building a closed Brayton cycle loop for energy conversion, heat pipe systems research for passive space heat rejection, developing computational programs for thermal loop safety analysis and other technology that may be used to improve efficiency and operation. Currently there is no specific mission that requires these technology development efforts; therefore, there is a certain degree of freedom in the organization and development efforts. This paper will present what has been achieved so far, what is the current development status, where efforts are heading and a proposed time table to meet development objectives.

  19. Development of nuclear spent fuel Maritime transportation scenario

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Min; Kang, Hyun Gook [KAIST, Daejeon (Korea, Republic of)

    2014-08-15

    Spent fuel transportation of South Korea is to be conducted through near sea because it is able to ship a large amount of the spent fuel far from the public comparing to overland transportation. The maritime transportation is expected to be increased and its risk has to be assessed. For the risk assessment, this study utilizes the probabilistic safety assessment (PSA) method and the notions of the combined event. Risk assessment of maritime transportation of spent fuel is not well developed in comparison with overland transportation. For the assessment, first, the transportation scenario should be developed and categorized. Categories are assorted into the locations, release aspects and exposure aspects. This study deals with accident that happens on voyage and concentrated on ship-ship collision. The collision accident scenario is generated with event tree analysis. The scenario will be exploited for the maritime transportation risk model which includes consequence and accident probability.

  20. The development of safety relief valve for nuclear service

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Chil Sung; Kim, Kang Tae; Kim, Ji Heon; Jang, Ki Jong [Smart Valve Com., Seoul (Korea, Republic of); Hong, Kee Seong [Korea Hydro and Nuclear Power Co., Ltd., Seoul (Korea, Republic of)

    2003-07-01

    Safety relief valve is the important equipment used to protect the pressure facility from overpressure. The objective of the study is the development of safety relief valve which protects the boiler and pressure vessel from over pressure by discharging or sucking the operating medium when the pressure of system is reaching the set pressure of the system. It is important to find out the relationship between trim shape and performance, so the characteristics of flow field at the inside of safety relief valve were investigated through computational fluid dynamics analysis. The study shows that safety relief valve is developed though the design using the analysis between flow characteristics and spring force, the experiential verification.

  1. Nuclear reactor pressure vessel-specific flaw distribution development

    Energy Technology Data Exchange (ETDEWEB)

    Rosinski, S.T.

    1992-09-01

    Vessel integrity predictions performed through fracture mechanics analysis of a pressurized thermal shock event have been shown to be significantly sensitive to the overall flaw distribution input. It has also been shown that modem vessel in-service inspection (ISI) results can be used for development of vessel flaw distribution(s) that are more representative of US vessels. This paper describes the development and application of a methodology to analyze ISI data for the purpose of flaw distribution determination. The resultant methodology considers detection reliability, flaw sizing accuracy, and flaw detection threshold in its application. Application of the methodology was then demonstrated using four recently acquired US PWR vessel inspection data sets. Throughout the program, new insight was obtained into several key inspection performance and vessel integrity prediction practice issues that will impact future vessel integrity evaluation. For example, the potential application of a vessel-specific flaw distribution now provides at least one method by which a vessel-specific reference flaw size applicable to pressure-temperature limit curves determination can be estimated. This paper will discuss the development and application of the methodology and the impact to future vessel integrity analyses.

  2. Nuclear reactor pressure vessel-specific flaw distribution development

    Energy Technology Data Exchange (ETDEWEB)

    Rosinski, S.T.

    1992-01-01

    Vessel integrity predictions performed through fracture mechanics analysis of a pressurized thermal shock event have been shown to be significantly sensitive to the overall flaw distribution input. It has also been shown that modem vessel in-service inspection (ISI) results can be used for development of vessel flaw distribution(s) that are more representative of US vessels. This paper describes the development and application of a methodology to analyze ISI data for the purpose of flaw distribution determination. The resultant methodology considers detection reliability, flaw sizing accuracy, and flaw detection threshold in its application. Application of the methodology was then demonstrated using four recently acquired US PWR vessel inspection data sets. Throughout the program, new insight was obtained into several key inspection performance and vessel integrity prediction practice issues that will impact future vessel integrity evaluation. For example, the potential application of a vessel-specific flaw distribution now provides at least one method by which a vessel-specific reference flaw size applicable to pressure-temperature limit curves determination can be estimated. This paper will discuss the development and application of the methodology and the impact to future vessel integrity analyses.

  3. North Korea's nuclear weapons development. Implications for future policy

    Energy Technology Data Exchange (ETDEWEB)

    Pollack, J.D.

    2010-07-01

    This essay assesses North Korea's long-standing quest for nuclear weapons; alternative strategies for inhibiting Pyongyang's weapons development; and the potential implications for regional security and nonproliferation should the Democratic People's Republic of Korea (DPRK) retain and enhance its weapons programs. North Korea's pursuit of a nuclear weapons capability has long provoked heated debate among policy makers and research analysts about the purposes of engagement with the North, reflecting the repeated frustrations in efforts to negotiate Korean denuclearization. These debates reflect widely divergent views of the North Korean regime; its sustainability as an autonomous political, economic, and military system; and the potential consequences of continued nuclear development in this isolated, highly idiosyncratic state. These questions assume additional salience as North Korea approaches a leadership succession for only the second time in its six-decade history. The effort to inhibit North Korea's pursuit of nuclear weapons is among the longest running and least successful sagas in international security and non-proliferation policy of the past quarter century. In early 2010, Pyongyang claims a rudimentary nuclear capability by possession of weaponized plutonium, the conduct of two nuclear tests, and advances in the production of enriched uranium as an alternative means of fissile material production, though the latter step is nominally justified as a source for reactor fuel. North Korea defends its pursuit of a nuclear deterrent to counter what Pyongyang deems existential threats posed by the United States.Despite the resumption of high-level diplomatic contact between Washington and Pyongyang in late 2009, realization of a non-nuclear Korean Peninsula remains a very remote prospect. The DPRK insists that a peace agreement between the U.S. and North Korea and hence the cessation of 'hostile DPRK-U.S. relations' are

  4. Status of Fuel Development and Manufacturing for Space Nuclear Reactors at BWX Technologies

    Science.gov (United States)

    Carmack, W. J.; Husser, D. L.; Mohr, T. C.; Richardson, W. C.

    2004-02-01

    New advanced nuclear space propulsion systems will soon seek a high temperature, stable fuel form. BWX Technologies Inc (BWXT) has a long history of fuel manufacturing. UO2, UCO, and UCx have been fabricated at BWXT for various US and international programs. Recent efforts at BWXT have focused on establishing the manufacturing techniques and analysis capabilities needed to provide a high quality, high power, compact nuclear reactor for use in space nuclear powered missions. To support the production of a space nuclear reactor, uranium nitride has recently been manufactured by BWXT. In addition, analytical chemistry and analysis techniques have been developed to provide verification and qualification of the uranium nitride production process. The fabrication of a space nuclear reactor will require the ability to place an unclad fuel form into a clad structure for assembly into a reactor core configuration. To this end, BWX Technologies has reestablished its capability for machining, GTA welding, and EB welding of refractory metals. Specifically, BWX Technologies has demonstrated GTA welding of niobium flat plate and EB welding of niobium and Nb-1Zr tubing. In performing these demonstration activities, BWX Technologies has established the necessary infrastructure to manufacture UO2, UCx, or UNx fuel, components, and complete reactor assemblies in support of space nuclear programs.

  5. Development of Export Control Comprehensive Management Model for Nuclear Power Plants and Others Projects

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chansuh; Seo, Hana; Choi, Sundo [Korea Institute of Nuclear Nonproliferation And Control, Daejeon (Korea, Republic of)

    2014-05-15

    It is required that there are lots of managements of care and concern if the project contains strategic items such as NPPs. The Korean nuclear industry and its related companies, such as the Korea Hydro and Nuclear Power (KHNP), are promoting greater exports of NPPs. It is likely that Korea will export more this technology to newcomer states in the future. As a result, the ROK has been improving its export control management system for NPPs. In keeping with this national effort, Korea Institute of Nuclear Nonproliferation And Control (KINAC) developed comprehensive export control management model for NPPs and other projects, in preparation for this projected growth in the industry. This model also applies to the nuclear export case of the UAE, aims to manage the project from bidding to the end of the contract. The recent Export Licensing of Nuclear Facility Technology was reflected in the Notice on Export and Import of Strategic Items in January 2014. Through this license, the large-scale project legislation framework was established. It can also minimize nonproliferation concerns of the international community through strict management. It is expected that the Korea will be able to enhance transparency and secure the nuclear use, while meeting nonproliferation purpose.

  6. Development model to public hearing for environmental licensing of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Vasques, Luciana Gomes; Aquino, Afonso Rodrigues de, E-mail: lu_vasques@usp.br, E-mail: araquino@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    The use of nuclear technology has always been a matter of concern from an environmental point of view. Although disputed, the generation of electricity in nuclear reactors was considered a source of clean emission in relation to emission of gases responsible for the greenhouse effect. In Brazil, nuclear activities are regulated and supervised by the Brazilian Commission of Nuclear Energy - CNEN. Environmental issues associated with nuclear activities are described by CONAMA, and the developments in this area are licensed by IBAMA, regardless of obtaining nuclear licenses issued by CNEN. Obtaining environmental licenses (prior, installation and operation) depends initially on preparing the Environmental Impact Study - EIS and the Environmental Impact Report - EIR, consisting of a presentation of EIS in language accessible to all. EIR is forwarded to bodies and entities with some connection to the enterprise, to be manifested with IBAMA about the relevance of its content. This information serves as a resource for Public Hearings, which are meetings organized by entrepreneurs, conducted by IBAMA, and rely on public participation, can be considered as a licensing step. Public Hearings are subject to subjectivity, and the model proposed in this research becomes more objective ill-defined, difficult to understand actions for the entrepreneur. (author)

  7. Nuclear energy option for energy security and sustainable development in India

    Energy Technology Data Exchange (ETDEWEB)

    Mallah, Subhash, E-mail: subhas_mallah2k1@yahoo.com [Shri Mata Vaishno Devi University, Katra, Jammu and Kashmir 182301 (India)

    2011-02-15

    India is facing great challenges in its economic development due to the impact on climate change. Energy is the important driver of economy. At present Indian energy sector is dominated by fossil fuel. Due to international pressure for green house gas reduction in atmosphere there is a need of clean energy supply for energy security and sustainable development. The nuclear energy is a sustainable solution in this context to overcome the environmental problem due to fossil fuel electricity generation. This paper examines the implications of penetration of nuclear energy in Indian power sector. Four scenarios, including base case scenario, have been developed using MARKAL energy modeling software for Indian power sector. The least-cost solution of energy mix has been measured. The result shows that more than 50% of the electricity market will be captured by nuclear energy in the year 2045. This ambitious goal can be expected to be achieved due to Indo-US nuclear deal. The advanced nuclear energy with conservation potential scenario shows that huge amounts of CO{sub 2} can be reduced in the year 2045 with respect to the business as usual scenario.

  8. Development of Nuclear Energy and Radiation Textbooks for Middle School Students

    Energy Technology Data Exchange (ETDEWEB)

    Kim, JaeRok; Lee, SeungKoo; Choi, YoonSeok; Hahm, YoungKyu; Lee, JiEun; Han, EunOk [Korea Academy of Nuclear Safety, Seoul (Korea, Republic of)

    2015-05-15

    Although the need for raising the ability to judge the media critically is increasing, no one can escape the influence of media in our information-based society. It is very difficult for the average individual to make proper value judgments in a social environment where incorrect or difficult to understand information about nuclear power and radiation is disseminated through the media. For this reason, there are many issues surrounding the use of radiation and nuclear power in South Korea. Therefore, relevant education must be provided to ensure social acceptance and appropriate judgments of the values and risks of nuclear energy and radiation, which are important for future generations. Taking the circumstances of the present time and the situation of information receivers, this study aimed to develop textbooks about nuclear energy and radiation targeting middle school students - the leaders of the next generation. developed to help future generations make value judgments based on appropriate information about nuclear energy and radiation. The themes and educational contents of the 13 lessons, to be delivered in one semester at middle school, were selected by the educational requirements of students, science teachers, and experts. The middle school students desired information that could be viewed from various perspectives, such as atomic bombs. The general trend in recent educational curriculum development suppresses national education course organizations and authorities and expands the autonomy and authority of regions and schools.

  9. Present status and history of nuclear data development for transmutation technology

    CERN Document Server

    Hasegawa, A

    2002-01-01

    A history of development of nuclear data from JENDL (Japanese Evaluated Nuclear Data Library)-1 to JENDL-3.3 and JENDL-HF (High energy File) and JENDL- Actinide File are stated. 5 nuclear data such as JENDL-1, JENDL-2, JENDL-3.1, JENDL-3.2 and JENDL-3.3 have been developed by JAERI. JENDL-1 for fast reactor (1977) has 66+6 nuclide and 15 MeV the largest energy. JENDL-2 for fast and light water reactor (1982) has 173+8 nuclide and 20 MeV. All-purpose nuclear data: JENDL-3.1 (1990) with 305+19 nuclide and 59 2nd gamma-ray data, JENDL-3.2 (1994) with 318+22 nuclide and 66 2nd gamma-ray data and JENDL-3.3 (2002) with 335+2 nuclide, 114 2nd gamma-ray data, 60 angular dependence neutron data and 20 MeV have been developed. JENDL-3.3 was opened at JAERI home page in May 2002. JENDL High Energy library consists of JENDL-HF, JENDL-Photonuclear Data File and JENDL-PKA/KERMA File. JENDL-HF includes nuclear reaction data of neutron and proton incidence, for example, total cross section, elastic scattering cross section a...

  10. Development of a Si-PM based alpha camera for plutonium detection in nuclear fuel facilities

    Science.gov (United States)

    Morishita, Yuki; Yamamoto, Seiichi; Izaki, Kenji; Kaneko, Junichi H.; Toi, Kohei; Tsubota, Youichi

    2014-05-01

    Alpha particles are monitored for detecting nuclear fuel material (i.e., plutonium and uranium) at nuclear fuel facilities. Currently, for monitoring the airborne contamination of nuclear fuel, only energy information measured by Si-semiconductor detectors is used to distinguish nuclear fuel material from radon daughters. In some cases, however, such distinguishing is difficult when the radon concentration is high. In addition, a Si-semiconductor detector is generally sensitive to noise. In this study, we developed a new alpha-particle imaging system by combining a Si-PM array, which is insensitive to noise, with a Ce-doped Gd3Al2Ga3O12(GAGG) scintillator, and evaluated our developed system's fundamental performance. The scintillator was 0.1-mm thick, and the light guide was 3.0 mm thick. An 241Am source was used for all the measurements. We evaluated the spatial resolution by taking an image of a resolution chart. A 1.6 lp/mm slit was clearly resolved, and the spatial resolution was estimated to be less than 0.6-mm FWHM. The energy resolution was 13% FWHM. A slight distortion was observed in the image, and the uniformity near its center was within ±24%. We conclude that our developed alpha-particle imaging system is promising for plutonium detection at nuclear fuel facilities.

  11. The Roles of Orphan Nuclear Receptors in the Development and Function of the Immune System

    Institute of Scientific and Technical Information of China (English)

    Ivan Dzhagalov; Nu Zhang; You-Wen He

    2004-01-01

    Hormones and their receptors regulate cell growth, differentiation and apoptosis and also play important roles in immune function. Recent studies on the subfamily of the orphan nuclear receptors known as retinoid-acid related orphan receptors (ROR) have shed important insights on the roles of this group of nuclear proteins in the development and function of the immune system. RORα regulates inflammatory cytokine production in both innate and adaptive immune system while RORγ regulates the normal development of T lymphocyte repertoire and secondary lymphoid organs. Cellular & Molecular Immunology. 2004;1(6):401-407.

  12. The Roles of Orphan Nuclear Receptors in the Development and Function of the Immune System

    Institute of Scientific and Technical Information of China (English)

    IvanDzhagalov; NuZhang; You-WenHe

    2004-01-01

    Hormones and their receptors regulate cell growth, differentiation and apoptosis and also play important roles in immune function. Recent studies on the subfamily of the orphan nuclear receptors known as retinoid-acid related orphan receptors (ROR) have shed important insights on the roles of this group of nuclear proteins in the development and function of the immune system. RORα regulates inflammatory cytokine production in both innate and adaptive immune system while RORγ, regulates the normal development of T lymphocyte repertoire and secondary lymphoid organs. Cellular & Molecular Immunology. 2004;1(6):401-407.

  13. Government, utilities, industry and universities: partners for nuclear development in Canada and abroad

    Energy Technology Data Exchange (ETDEWEB)

    Hurst, D.G.; Woolston, J.E.

    1971-09-15

    In Canada, eleven power reactors installed or committed at four sites will provide 5 520 MW(e) for an investment of $1 800 million. Uranium production during the decade 1958-1967 totalled 79 700 tonnes U{sub 3}O{sub 8} worth $1 621 million. For nuclear research, development and control, the federal government employs about 6 000 people and spends about $80 million/year which includes the cost of operating three major research reactors (> 30 MW each). Aggregate commercial isotope production has reached 14 megacuries, and Canada has about 3 000 licensed users. Three power and two research reactors of Canadian design are or will be installed in developing countries overseas. Legislation in 1946 made atomic energy a federal responsibility and established an Atomic Energy Control Board. The Board's regulations, which deal primarily with health, safety and security, are administered with the co-operation of appropriate departments of the federal and provincial governments. Large-scale nuclear research began in 1941 and continued under the National Research Council until 1952 when the federal government created a public corporation, Atomic Energy of Canada Limited, to take over both research and the exploitation of atomic energy. Another public corporation, Eldorado Nuclear Limited, conducts research and development on the processing of uranium and operates Canada's only uranium refinery, but prospecting and mining is undertaken largely by private companies. The publicly owned electrical utilities of Ontario and Quebec operate nuclear power stations and participate, with governments, in their financing. Private industry undertakes extensive development and manufacturing, mainly under contract to Atomic Energy of Canada Limited and the utilities, and industry has formed its own Canadian Nuclear Association. Canadian universities undertake nuclear research, and receive significant government support; one has operated a research reactor since 1959. Canada

  14. Nuclear energy and sustainable development: contradiction or challenge?

    Energy Technology Data Exchange (ETDEWEB)

    Laes, E.; Meskens, G. [SCK.CEN, Belgian Nuclear Research Centre, Mol (Belgium)

    2001-07-01

    The concept of sustainable development is widely accepted as a principle for decision-making. However, it needs to be put into operation. Two classical approaches, cost-benefit analysis and multi-criteria analysis, are not suitable on account of the underlying rational choice theory and value system. Insights from these methods need to be complemented by the inherently pluralistic approach of cultural theory. This offers the prospects of the identification of all relevant criteria for the comparison of different energy vectors, broadening the perspective through an interdisciplinary working process, confronting uncertainty at a fundamental level, and the explicit integration of values and world views. (author)

  15. Some recent developments in nuclear charged particle detectors

    Energy Technology Data Exchange (ETDEWEB)

    Stelzer, H.

    1980-08-01

    The latest developments of large-area, position sensitive gas-filled ionization chambers are described. Multi-wire-proportional chambers as position-sensing and parallel-plate-avalanche counters as time-sensing detectors at low pressure (5 torr) have proven to be useful and reliable instruments in heavy ion physics. Gas (proportional) scintillation counters, used mainly for x-ray spectroscopy, have recently been applied as particle detectors. Finally, a brief description of a large plastic scintillator spectrometer, the Plastic Ball, is given and some of the first test and calibration data are shown.

  16. Nuclear Fuel Design Technology Development for the Future Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Yang Hyun; Lee, Byung Ho; Cheon, Jin Sik; Oh, Je Yong; Yim, Jeong Sik; Sohn, Dong Seong; Lee, Byung Uk; Ko, Han Suk; So, Dong Sup; Koo, Dae Seo

    2006-04-15

    The test MOX fuels have been irradiated in the Halden reactor, and their burnup attained 40 GWd/t as of October 2005. The fuel temperature and internal pressure were measured by the sensors installed in the fuels and test rig. The COSMOS code, which was developed by KAERI, well predicted in-reactor behavior of MOX fuel. The COSMOS code was verified by OECD-NEA benchmarks, and the result confirmed the superiority of COSMOS code. MOX in-pile database (IFA-629.3, IFA-610.2 and 4) in Halden was also used for the verification of code. The COSMOS code was improved by introducing Graphic User Interface (GUI) and batch mode. The PCMI analysis module was developed and introduced by the new fission gas behavior model. The irradiation test performed under the arbitrary rod internal pressure could also be analyzed with the COSMOS code. Several presentations were made for the preparation to transfer MOX fuel performance analysis code to the industry, and the transfer of COSMOS code to the industry is being discussed. The user manual and COSMOS program (executive file) were provided for the industry to test the performance of COSMOS code. To envisage the direction of research, the MOX fuel research trend of foreign countries, specially focused on USA's GENP policy, was analyzed.

  17. The IAEA technical cooperation programme and nuclear medicine in the developing world: objectives, trends, and contributions.

    Science.gov (United States)

    Casas-Zamora, Juan Antonio; Kashyap, Ridhi

    2013-05-01

    The International Atomic Energy Agency's technical cooperation (TC) programme helps Member States in the developing world with limited infrastructure and human resource capacity to harness the potential of nuclear technologies in meeting socioeconomic development challenges. As a part of its human health TC initiatives, the Agency, through the TC mechanism, has the unique role of promoting nuclear medicine applications of fellowships, scientific visits, and training courses, via technology procurement, and in the past decade has contributed nearly $54 million through 180 projects in supporting technology procurement and human resource capacity development among Member States from the developing world (low- and middle-income countries). There has been a growing demand in nuclear medicine TC, particularly in Africa and ex-Soviet Union States where limited infrastructure presently exists, based on cancer and cardiovascular disease management projects. African Member States received the greatest allocation of TC funds in the past 10 years dedicated to building new or rehabilitating obsolete nuclear medicine infrastructure through procurement support of single-photon emission computed tomography machines. Agency support in Asia and Latin America has emphasized human resource capacity building, as Member States in these regions have already acquired positron emission tomography and hybrid modalities (positron emission tomography/computed tomography and single-photon emission computed tomography/computed tomography) in their health systems. The strengthening of national nuclear medicine capacities among Member States across different regions has enabled stronger regional cooperation among developing countries who through the Agency's support and within the framework of regional cooperative agreements are sharing expertise and fostering the sustainability and productive integration of nuclear medicine within their health systems.

  18. Development of nuclear design criteria for neutron spallation sources

    Energy Technology Data Exchange (ETDEWEB)

    Sordo, F.; Abanades, A. [E.T.S. Industriales, Madrid Polytechnic University, UPM, J.Gutierrez Abascal, 2 -28006 Madrid (Spain)

    2008-07-01

    Spallation neutron sources allow obtaining high neutronic flux for many scientific and industrial applications. In recent years, several proposals have been made about its use, notably the European Spallation Source (ESS), the Japanese Spallation Source (JSNS) and the projects of Accelerator-Driven Subcritical reactors (ADS), particularly in the framework of EURATOM programs. Given their interest, it seems necessary to establish adequate design basis for guiding the engineering analysis and construction projects of this kind of installations. In this sense, all works done so far seek to obtain particular solutions to a particular design, but there has not been any general development to set up an engineering methodology in this field. In the integral design of a spallation source, all relevant physical processes that may influence its behaviour must be taken into account. Neutronic aspects (emitted neutrons and their spectrum, generation performance..), thermomechanical (energy deposition, cooling conditions, stress distribution..), radiological (spallation waste activity, activation reactions and residual heat) and material properties alteration due to irradiation (atomic displacements and gas generation) must all be considered. After analysing in a systematic manner the different options available in scientific literature, the main objective of this thesis was established as making a significant contribution to determine the limiting factors of the main aspects of spallation sources, its application range and the criteria for choosing optimal materials. To achieve this goal, a series of general simulations have been completed, covering all the relevant physical processes in the neutronic and thermal-mechanical field. Finally, the obtained criteria have been applied to the particular case of the design of the spallation source of subcritical reactors PDX-ADS and XT-ADS. These two designs, developed under the European R and D Framework Program, represent nowadays

  19. Nuclear Industry Input to the Development of Concepts for the Consolidated Storage of Used Nuclear Fuel - 13411

    Energy Technology Data Exchange (ETDEWEB)

    Phillips, Chris; Thomas, Ivan; McNiven, Steven [EnergySolutions Federal EPC., 2345 Stevens Drive, Richland, WA, 99354 (United States); Lanthrum, Gary [NAC International, 3930 East Jones Bridge Road, Norcross, GA, 30092 (United States)

    2013-07-01

    EnergySolutions and its team partners, NAC International, Exelon Nuclear Partners, Talisman International, TerranearPMC, Booz Allen Hamilton and Sargent and Lundy, have carried out a study to develop concepts for a Consolidated Storage Facility (CSF) for the USA's stocks of commercial Used Nuclear Fuel (UNF), and the packaging and transport provisions required to move the UNF to the CSF. The UNF is currently stored at all 65 operating nuclear reactor sites in the US, and at 10 shutdown sites. The study was funded by the US Department of Energy and followed the recommendations of the Blue Ribbon Commission on America's Nuclear Future (BRC), one of which was that the US should make prompt efforts to develop one or more consolidated storage facilities for commercial UNF. The study showed that viable schemes can be devised to move all UNF and store it at a CSF, but that a range of schemes is required to accommodate the present widely varying UNF storage arrangements. Although most UNF that is currently stored at operating reactor sites is in water-filled pools, a significant amount is now dry stored in concrete casks. At the shutdown sites, the UNF is dry stored at all but two of the ten sites. Various types of UNF dry storage configurations are used at the operating sites and shutdown sites that include vertical storage casks that are also licensed for transportation, vertical casks that are licensed for storage only, and horizontally orientated storage modules. The shutdown sites have limited to nonexistent UNF handling infrastructure and several no longer have railroad connections, complicating UNF handling and transport off the site. However four methods were identified that will satisfactorily retrieve the UNF canisters within the storage casks and transport them to the CSF. The study showed that all of the issues associated with the transportation and storage of UNF from all sites in the US can be accommodated by adopting a staged approach to the

  20. Integration of Nuclear Safeguards Infrastructure Development with UNSCR 1540 Implementation - Context and Challenges

    Energy Technology Data Exchange (ETDEWEB)

    Dreicer, M; Essner, J

    2008-11-03

    On 28 April 2004, the UN Security Council adopted Resolution 1540 (2004), obliging States, inter alia, to refrain from supporting by any means non-State actors from developing, acquiring, manufacturing, possessing, transporting, transferring or using nuclear, chemical or biological weapons and their delivery systems. It imposes binding obligations on all States to establish domestic controls to prevent the proliferation of nuclear, chemical and biological weapons, and their means of delivery, including by establishing appropriate controls over related materials. This mandate was extended an additional two years with the adoption of Resolution 1673 (2006) and an additional three years with the adoption of Resolution 1810 (2008). UNSCR 1540 is a key nonproliferation and counterterrorism tool that needs to be implemented well. Its obligations are a core part of nuclear infrastructure development.

  1. Personnel involved in the development of nuclear standards in the United States, 1975

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, E.B. (ed.)

    1976-05-01

    The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The Directory has four major sections: personnel, employers, committees, and a KWIC Index of committee titles. The Directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities.

  2. Development of automated nondestructive inspection system for BMI nozzles in nuclear vessel

    Energy Technology Data Exchange (ETDEWEB)

    Park, Joon Soo; Lee, Won Kun; Han, Won Jin; Lee, Sun Ho; Seong, Un Hak [Doosan Heavy Industries and Construction Co., Ltd., Changwon (Korea, Republic of)

    2013-02-15

    BMI nozzles in bottom head of the nuclear vessel are one of major components in nuclear power plants. The BMI nozzles have high possibility to generate PWSCC(primary water stress corrosion crack) according to recent foreign case although operation temperature is lower then the upper head of the nuclear vessel. Thus, nondestructive inspection of the BMI nozzles is required. But, inspection of BMI nozzles is not easy since the BMI nozzles placed in high radiated area and inside the nozzles filled with boric acid. Thus, in this study, a TOFD transducer for inspection of BMI and automated scanner system with water were developed. Also, validation of performance of the developed transducer and system are performed using specimens with artificial defects.

  3. Developing countries' motivation to use nuclear technology. Motivation von Drittweltlaendern zur Nutzung der Kernenergie

    Energy Technology Data Exchange (ETDEWEB)

    Ratsch, U. (FEST, Heidelberg (Germany))

    1990-08-01

    Governments of various developing countries see nuclear energy as an important tool for at least three political goals: Firstly, the expected rise in future energy demand, so they argue, can only be met if nuclear electricity production in the Third World is expanded. Fossil sources are supposed to become increasingly scarce and expensive, and they are also seen to be ecologically damaging. Technologies to harness renewable energy sources are not yet mature and still too costly. Secondly, nuclear technology is seen as one of the most advanced technologies. Mastering of it might help to diminish the technological gap between the First and the Third World. Thirdly, scientific progress in developing countries is hoped to be accelerated by operating research reactors in these countries. All of these arguments ought to be taken as serious motivations. (orig./HSCH).

  4. Personnel involved in the development of nuclear standards in the United States, 1976

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, E.B. (ed.)

    1977-03-01

    The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The directory has four major sections: personnel, employers, committees, and a KWIC index of committee titles. The directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities.

  5. New developments in tele-robotics for the nuclear fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Desbats, P.; Geffard, F.; Garrec, P.; Perrot, Y.; Measson, Y.; Russotto, F.X. [CEA LIST, Bat 476 - DTSI, 91191 Gif-sur-Yvette (France); Thro, J.F.; Piolain, G. [AREVA NC, 1 place Jean Millier, 92084 Paris - La Defense (France)

    2009-06-15

    In the nuclear facilities of the nuclear fuel cycle, as fuel manufacturing and reprocessing plants, power reactors, waste temporary storage units.., materials handling must be carried out remotely, taking into account the high nuclear radiating environment. Tele-robotics technologies clearly aim to improve the working conditions of human operators with respect to the ALARA principle. The Laboratory of Applied Research on Software-intensive Technologies of the French Nuclear Commission (CEA LIST) has developed, in collaboration with AREVA NC company, a wide range of robotics and remote handling technologies for the maintenance of the operating nuclear fuel cycle facilities and for the dismantling of the older nuclear facilities having shut down. The paper gives an overview of the progress of these developments which cover a wide range of technologies, like force-feedback master-salve systems, master arms, slave manipulators, long range inspection robots, radiation tolerant electronic systems, interactive environment modeling and simulation software, as well as generic control and simulation software tools for tele-operated systems. Several recent applications are presented in the paper: - electrical industrial robot arm remotely operated with force feedback; - hot cell tele-manipulator remotely operated with an electrical master arm; - hydraulic tele-manipulator with its embedded electronics controller; - modular articulated arm for inspection of blind cells or vessel. The paper shows how the results of this R and D program, carried out by CEA LIST along 15 years in the framework of industrial partnerships, will be valuable for the introduction of new robotics and remote handling technologies in current and future nuclear hazardous facilities. (authors)

  6. 后福岛时期我国核电的发展%China's Nuclear Power Development After Fukushima Nuclear Power Plant Accident

    Institute of Scientific and Technical Information of China (English)

    叶奇蓁

    2012-01-01

    摘要:靠性及发展核电的必要性进行了探讨;介绍了福岛事故后美、法、俄、英、韩等核电国家均表示坚持发展核电的立场,并通过审查测试得出了目前的核电站是安全的结论。其次,论述了福岛事故后我国对核电站的安全检查以及核电设计中采取的相关安全措施,表明我国核电站的安全性是有保障的。然后,阐述了引进的三代核电APl000及EPR技术的特点;自主开发的三代核电技术在技术性能和安全水准上与国际先进水平相当。最后,分析了内陆地区核电建设的必要性和可行性,建议积极推进内陆核电站建设。。%After the Fukmshima Daiichi nuclearplant accident, the safety of developing nuclear power has aroused widely attentions, and governments have taken active measures to deal with the influence of this accident. Nuclear safety and the necessity of the nuclear power development were discussed firstly. After the Fukushima incident, United States, France, Russia, England, South Korea and other nuclear countries said that they all adhere to develop nuclear power actively. Through examinations and tests of the current nuclear power stations, it can be concluded that all the nuclear power stations are safe at present. After the accident, safety inspections as well as related safety measures which had been taken in China's nuclear power design were introduced, showing that the safety of nuclear power can be guaranteed in China. The characteristics of the introduced third-generation AP1000 and EPR unit nuclear power technologies were described and compared; results showed that performances of China's independently developed thirdgeneration nuclear power technologies have reached the international advanced level. Through the analysis on the necessity and the feasibility of the inland nuclear power construction, it has been suggested that the construction of the inland nuclear power station shall be put

  7. DUPIC nuclear fuel manufacturing and process technology development

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-05-01

    In this study, the DUPIC fuel fabrication technology for DUPIC pellet and element satisfying the standard specification was verified through (1) the improvement of fabrication technology and equipment, (2) remote operation of fuel manufacturing and inspection equipment installed at DFDF and (3) the study on the material properties of DUPIC fuel. The blending process was newly developed for making DUPIC powder composition homogeneous, and mixing process was added to the DUPIC process flow for fabricating crack-free pellets. A series of fabrication experiments were carried out in terms of various process conditions. Based on these experimental results, the optimal process flow and conditions for DUPIC fuel fabrication were established. 6 DUPIC elements and 6 mini-elements for irradiation test in HANARO was successfully fabricated using 7.4 kg of spent PWR fuel in 2000. The process qualification tests has been performed using 10 kg of spent PWR fuel since May 2001. The optimal DUPIC fuel fabrication process meeting AECL's quality requirements has been established and qualified. Quality assurance system for DUPIC fuel fabrication was also established in cooperation of AECL.

  8. Development of a remote controlled robot system for monitoring nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Hee Gon; Song, Myung Jae; Shin, Hyun Bum; Oh, Gil Hwan; Maeng, Sung Jun; Choi, Byung Jae; Chang, Tae Woo [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Lee, Bum Hee; Yoo, Jun; Choi, Myung Hwan; Go, Nak Yong; Lee, Kee Dong; Lee, Young Dae; Cho, Hae Kyeng; Nam, Yoon Suk [Electric and Science Research Center, (Korea, Republic of)

    1996-12-31

    It`s a final report of the development of remote controlled robot system for monitoring the facilities in nuclear power plant and contains as follows, -Studying the technologies in robot developments and analysing the requirements and working environments - Development of the test mobile robot system - Development of the mobile-robot - Development of the Mounted system on the Mobile robot - Development of the Monitoring system - Mobil-robot applications and future study. In this study we built the basic technologies and schemes for future robot developments and applications. (author). 20 refs., figs.

  9. Technology development on the assessment of structural integrity of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Jeong Moon; Choun, Y. S.; Choi, I. K. and others

    1999-04-01

    Nuclear power plants in Korea show drop off in their performance and safety margin as the age of plants increase. The reevaluation of Kori-1 Unit on its performance and safety for life extension is expected in the near future. However, technologies and information related are insufficient to quantitatively estimate them. The final goal of this study is to develop the basic testing and evaluation techniques related with structural integrity of important nuclear equipment and structures. A part of the study includes development of equipment qualification technique. To ensure the structural integrity of structures, systems, and equipment in nuclear power plants, the following 5 research tasks were performed in the first year. - Analysis of dynamic characteristics of reactor internals - Analysis of engineering characteristics of instrumental earthquakes recorded in Korea - Analysis of ultimate pressure capacity and failure mode of containments building - Development of advanced NDE techniques using ultrasonic resonance scattering - Development of equipment qualification technique against vibration aging. These technologies developed in this study can be used to ensure the structural safety of operational nuclear power plants, and for the long-term life management. (author)

  10. Technology development on the assessment of structural integrity of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Jeong Moon; Choun, Y. S.; Choi, I. K. and others

    1999-04-01

    Nuclear power plants in Korea show drop off in their performance and safety margin as the age of plants increase. The reevaluation of Kori-1 Unit on its performance and safety for life extension is expected in the near future. However, technologies and information related are insufficient to quantitatively estimate them. The final goal of this study is to develop the basic testing and evaluation techniques related with structural integrity of important nuclear equipment and structures. A part of the study includes development of equipment qualification technique. To ensure the structural integrity of structures, systems, and equipment in nuclear power plants, the following 5 research tasks were performed in the first year. - Analysis of dynamic characteristics of reactor internals - Analysis of engineering characteristics of instrumental earthquakes recorded in Korea - Analysis of ultimate pressure capacity and failure mode of containments building - Development of advanced NDE techniques using ultrasonic resonance scattering - Development of equipment qualification technique against vibration aging. These technologies developed in this study can be used to ensure the structural safety of operational nuclear power plants, and for the long-term life management. (author)

  11. Irradiation characteristics examination technology development of irradiated nuclear material and high burn-up fuels

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Kwon Pyo; Choo, Y. S.; Oh, Y. W. [and others

    2002-12-01

    The research and development for the first year of the project are performed through specialization of researchers, information from aborad and international cooperation, securement of advanced nuclear technology, development and installation of test equipment, application of external man-power, establishment of advanced test techniques, and certified test method. 1. Absolute efficiency measurement examination technology development of gamma scanning system 2. Sample preparation technology development of SEM and EPMA for micro-structural observation and chemical composition analysis 3. Irradiated high burn-up nuclear fuel transportation and test for PWR 4. Development of hot cell examination techniques and equipment 5. Acquirement of KOLAS system. In addition to the project, the following activities are carried out as follows; - PIE of Hanaro fuel(KH99H-001) - PIE of U-Mo advanced nuclear fuel irradiated at Hanaro - PIE of Hi-MET advanced nuclear fuel irradiated at Hanaro - PIE of DUPIC project - Hot cell examination of Hanaro irradiated capsule - Leaching test of PWR fuels - Surveillance test of PWR vessels - Mechanical test of CANDU pressure tubes.

  12. Development and Enhancement of Web-based Nuclear Education System and It's Enhancement

    Energy Technology Data Exchange (ETDEWEB)

    Rho, Sipyo; Lee, K. B.; Nam, Y. M; Kim, H. K.; Hwang, I. A.; Yang, S. W.; Nam, J. S.; Yoo, H. W.

    2012-02-15

    To deliver rapidly changing technologies effectively and economically, E-learning in the field of nuclear technology is being done gradually. In the first year of this project, 'Development and Enhancement of Web-based Nuclear Education System; we had established a server system, fitting-up several home pages in NTC(Nuclear Training and Education Center in KAERI) and newly developed LMS(Learning Management System). We had selected a MOODLE for it is one of popular open source in LMS field, and connected to the ANENT(Asian Nuclear in Education for Nuclear Technology) web portal, which is co-operating with IAEA/NKM. We had produced e-learning content mainly composed of the video clip that was taken by making a film of the lecturing in the course of training and education in NTC. The running time of the content is 100 hours totally. This e-learning content is going to reinforce by adding quiz and Q and A. Another activity is web-conferencing between NWU in South Africa and KAERI, which executed 4 times successfully. We are going to make a pre-course for the foreigners who will take part in our training and education course.

  13. A basic study for development of environmental standard review plan of Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Chang Hyun; Cho, Jae Seon; You, Young Woo [Seoul Nationl Univ., Seoul (Korea, Republic of)] (and others)

    1999-12-15

    In this study is performed a basic study to be ready for the development and detail analysis of NUREG-1555 ESRP. As a fundamental research for literature survey and development of draft review plan, review and translation of NUREG-1555 published by NRC, and which is applied to licensing procedure of Nuclear Power Plants are included. These provided the basic information for the developments of the environmental standard review plan.

  14. Ship-Based Nuclear Energy Systems for Accelerating Developing World Socioeconomic Advance

    Science.gov (United States)

    Petroski, Robert; Wood, Lowell

    2014-07-01

    Technological, economic, and policy aspects of supplying energy to newly industrializing and developing countries using ship-deployed nuclear energy systems are described. The approach analyzed comprises nuclear installations of up to gigawatt scale deployed within currently mass-produced large ship hulls which are capable of flexibly supplying energy for electricity, water desalination and district heating-&-cooling with low latencies and minimized shoreside capital expenditures. Nuclear energy is uniquely suited for mobile deployment due to its combination of extraordinary energy density and high power density, which enable enormous supplies of energy to be deployed at extremely low marginal costs. Nuclear installations on ships also confer technological advantages by essentially eliminating risk from earthquakes, tsunamis, and floods; taking advantage of assured access to an effectively unlimited amount of cooling water, and involving minimal onshore preparations and commitments. Instances of floating nuclear power stations that have been proposed in the past, some of which are currently being pursued, have generally been based on conventional LWR technology, moreover without flexibility or completeness of power output options. We consider nuclear technology options for their applicability to the unique opportunities and challenges of a marine environment, with special attention given to low-pressure, high thermal margin systems with continuous and assured afterheat dissipation into the ambient seawater. Such systems appear promising for offering an exceptionally high degree of safety while using a maximally simple set of components. We furthermore consider systems tailored to Developing World contexts, which satisfy societal requirements beyond electrification, e.g., flexible sourcing of potable water and HVAC services, servicing time-varying user requirements, and compatibility with the full spectrum of local renewable energy supplies, specifically including

  15. SCINTILLA A European project for the development of scintillation detectors and new technologies for nuclear security

    CERN Document Server

    Alemberti, A; Botta, E; De Vita, R; Fanchini, E; Firpo, G

    2014-01-01

    Europe monitors transits using radiation detectors to prevent illicit trafficking of nuclear materials. The SCINTILLA project aims to develop a toolbox of innovative technologies designed to address different usage cases. This article will review the scope, approach, results of the first benchmark campaign and future plans of the SCINTILLA project.

  16. Development of Nuclear Renewable Oil Shale Systems for Flexible Electricity and Reduced Fossil Fuel Emissions

    Energy Technology Data Exchange (ETDEWEB)

    Daniel Curtis; Charles Forsberg; Humberto Garcia

    2015-05-01

    We propose the development of Nuclear Renewable Oil Shale Systems (NROSS) in northern Europe, China, and the western United States to provide large supplies of flexible, dispatchable, very-low-carbon electricity and fossil fuel production with reduced CO2 emissions. NROSS are a class of large hybrid energy systems in which base-load nuclear reactors provide the primary energy used to produce shale oil from kerogen deposits and simultaneously provide flexible, dispatchable, very-low-carbon electricity to the grid. Kerogen is solid organic matter trapped in sedimentary shale, and large reserves of this resource, called oil shale, are found in northern Europe, China, and the western United States. NROSS couples electricity generation and transportation fuel production in a single operation, reduces lifecycle carbon emissions from the fuel produced, improves revenue for the nuclear plant, and enables a major shift toward a very-low-carbon electricity grid. NROSS will require a significant development effort in the United States, where kerogen resources have never been developed on a large scale. In Europe, however, nuclear plants have been used for process heat delivery (district heating), and kerogen use is familiar in certain countries. Europe, China, and the United States all have the opportunity to use large scale NROSS development to enable major growth in renewable generation and either substantially reduce or eliminate their dependence on foreign fossil fuel supplies, accelerating their transitions to cleaner, more efficient, and more reliable energy systems.

  17. Development of Internal Dose Assessment Program for Nuclear Power Plant Employees

    Energy Technology Data Exchange (ETDEWEB)

    Song, Myung Jae; Kang, Duck Won; Maeng, Sung Jun; Kim, Hee Geun; Son, Soon Whan; Lim, Young Kee; Son, Joong Kwon; Park, Keyoung Rock [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Jang, See Young; Ha, Jong Woo; Suh, Keyoung Won [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Oh, Oak Doo; Lee, Joong Woo; Yoon, Sung Sik [Yonsei University, Seoul (Korea, Republic of)

    1996-12-31

    Internal exposure monitoring based on new concept of radiation protection. Analysis and Performance test of the in vivo systems being operated in nuclear power plants in Korea. Design and fabrication of humanoid phantom for calibration of in vivo system. Development of internal dose evaluation code based on the ICRP 30 dosimetric model. (author). 44 refs., figs.

  18. Development of Career Opportunities for Technicians in the Nuclear Medicine Field. Final Report.

    Science.gov (United States)

    Technical Education Research Center, Cambridge, MA.

    This report describes a nationally coordinated program development project whose purpose was to catalyze the implementation of needed postsecondary educational programs in the field of nuclear medicine technology (NMT). The NMT project was carried out during the six year period 1968-74 in cooperation with more than 36 community/junior colleges and…

  19. Development for analysis system of rods enrichment of nuclear fuels; Desarrollo de un sistema de analisis de enriquecimiento de barras de combustible nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Rojas C, E.L

    1998-11-01

    Nuclear industry is strongly regulated all over the world and quality assurance is important in every nuclear installation or process related with it. Nuclear fuel manufacture is not the exception. ININ was committed to manufacture four nuclear fuel bundles for the CFE nucleo electric station at Laguna Verde, Veracruz, under General Electric specifications and fulfilling all the requirements of this industry. One of the quality control requisites in nuclear fuel manufacture deals with the enrichment of the pellets inside the fuel bundle rods. To achieve the quality demanded in this aspect, the system described in this work was developed. With this system, developed at ININ it is possible to detect enrichment spikes since 0.4 % in a column of pellets with a 95 % confidence interval and to identify enrichment differences greater than 0.2 % e between homogeneous segments, also with a 95 % confidence interval. ININ delivered the four nuclear fuel bundles to CFE and these were introduced in the core of the nuclear reactor of Unit 1 in the fifth cycle. Nowadays they are producing energy and have shown a correct mechanical performance and neutronic behavior. (Author)

  20. Development of alkaline solution separations for potential partitioning of used nuclear fuels

    Energy Technology Data Exchange (ETDEWEB)

    Jarvinen, Gordon D [Los Alamos National Laboratory; Runde, Wolfgang H [Los Alamos National Laboratory; Goff, George S [Los Alamos National Laboratory

    2009-01-01

    The processing of used nuclear fuel in alkaline solution provides potentially useful new selectivity for separating the actinides from each other and f rom the fission products. Over the ast decade, several research teams around the world have considered dissolution of used fuel in alkaline solution and further partitioning in this medium as an alternative to acid dissolution. The chemistry of the actinides and fission products in alkaline soilltion requires extensive investigation to more carefully evaluate its potential for developing useful separation methods for used nuclear fueI.

  1. Development of nuclear magnetic and quadrupole resonance spectroscopy under 10 GPa class pressure

    Energy Technology Data Exchange (ETDEWEB)

    Kobayashi, R; Uchida, Y; Hirayama, K; Yamazaki, T; Fukazawa, H; Kohori, Y [Department of Physics, Graduate School of Science, Chiba University, Chiba 263-8522 (Japan); Takeshita, N, E-mail: hideto@nmr.s.chiba-u.ac.j [JST, TRIP, Chiyoda-ku, Tokyo 102-0075 (Japan)

    2010-03-01

    The high pressure nuclear magnetic resonance (NMR) and nuclear quadrupole resonance (NQR) are conventionally performed up to 3 GPa using piston cylinder cell. However, the NMR/NQR measurements beyond this pressure range are scarcely performed owing to the technical difficulty. Recently, we developed new high pressure NMR/NQR technique using cubic anvil apparatus in which highly hydrostatic pressure was obtained. Using the new method, the {sup 63}Cu-NQR signal of Cu{sub 2}O was observed up to 7.2GPa with high sensitivity. The use of MgO gasket in mini-cubic anvil apparatus was examined for enlarging pressure range.

  2. Status and development of nuclear techniques for commercial application in Sichuan

    Energy Technology Data Exchange (ETDEWEB)

    Chen Hao; Pan Pingchuan; Chen Zhuping; Zhu Yun; Chao Xiaochuan [Sichuan Province Institute of Nuclear Technology Application, Chengdu, Sichuan (China)

    2001-03-01

    This article presents information on fields of radiation techniques in Sichuan and their potential development in future. Sichuan is one of biggest provinces and is a center of economy and art in the southwest of China. Research of nuclear technology began from 1960. The studies at the beginning had focused on agriculture, radiation chemistry industry and radiation medicine. Over the past 30 years, nuclear techniques are used in a wide range of applications, from food preservation to crosslinking. They play an increasingly valuable and often unique role in Sichuan economy. (J.P.N.)

  3. Annual report of Power Reactor and Nuclear Fuel Development Corporation, fiscal year 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    This was the Annual Report of the Power Reactor and Nuclear Fuel Development Corporation, Fiscal Year of 1994. In this report, the following 12 items are described: (1) Development of the fast breeding reactor; (a) operation of the fast experimental reactor, `Joyo`, (b) construction and trial operation of the fast breeding prototype reactor, `Monju`, and (c) R and D of FBR; (2) Development of the new type conversion reactor; (a) operation of prototype reactor, `Fugen`, and (b) R and D of ATR; (3) Development of uranium mining and conversion; (4) Development of uranium concentration technology; (5) Development of plutonium fuel; (a) preparation of the MOX fuel, (b) preparation facility construction of the MOX fuel, (c) R and D of plutonium fuel. and (d) technical development of plutonium mixing and conversion; (6) Reprocessing of spent fuel; (7) Environmental technology development of radioactive waste; (8) Creative and innovative R and D; (9) Management and nuclear non-proliferation countermeasure of nuclear matter; (10) Safety management and safety study; (11) Related common business; and (12) General management business. (G.K.)

  4. Prolonged interval between fusion and activation impairs embryonic development by inducing chromosome scattering and nuclear aneuploidy in pig somatic cell nuclear transfer.

    Science.gov (United States)

    You, Jinyoung; Song, Kilyoung; Lee, Eunsong

    2010-01-01

    The aim of the present study was to examine the effect of various intervals between electrofusion and activation (FA interval) on the nuclear remodelling and development of somatic cell nuclear transfer (SCNT) embryos in pigs. Reconstructed oocytes were activated at 0 (simultaneous fusion and activation; SFA), 1, 2 and 3 h (delayed activation) after electrofusion; these groups were designated as DA1, DA2 and DA3, respectively. When oocyte nuclear status was examined at 0.5, 1, 2 and 3 h after electrofusion, the incidence of chromosome scattering was increased (P or=3) pseudopronuclei (PPN) (0.0% of SFA; 5.3% of DA1; 21.7% of DA2; and 33.5% of DA3). The development of SCNT embryos to the blastocyst stage was decreased (P nuclear aneuploidy.

  5. NRC nuclear waste management technical support in the development of nuclear waste form criteria. Task 4. Test development review

    Energy Technology Data Exchange (ETDEWEB)

    Czyscinski, K.S.; Swyler, K.J.; Klamut, C.J.

    1980-05-01

    This interim report concerns the development of testing procedures to assess the performance of waste packages to be used for high-level waste disposal in geologic repositories. Single component testing of the waste package is determined to be a workable strategy for testing and evaluation in terms of NRC release rate criteria. An initial literature review has identified key tests and those variables which must be included in testing procedures to simulate repository conditions. The range of these conditions remains to be determined precisely. Methods for leach, corrosion, and sorption testing are reviewed and initial recommendations made for preferred procedures. A combination of static and dynamic tests is needed to evaluate waste package component performance. Additional research is necessary in certain areas both to establish reliable testing methods and to define the range of testing variables. Research recommendations are included in the report. Ancillary measurements will be required to ensure that key tests rigorously assess the durability of waste package components under anticipated repository conditions. In particular, radiation effects in the repository environment must be considered and, where necessary, simulated during critical testing. Research is recommended to aid in determining when and how this should be done.

  6. Development of polyphase ceramics for the immobilization of high-level Defense nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Morgan, P.E.D.; Harker, A.B.; Clarke, D.R.; Flintoff, J.J.; Shaw, T.M.

    1983-02-25

    The report contains two major sections: Section I - An Improved Polyphase Ceramic for High-Level Defense Nucleation Waste reports the work conducted on titanium-silica based ceramics for immobilizing Savannah River Plant waste. Section II - Formulation and Processing of Alumina Based Ceramic Nuclear Waste Forms describes the work conducted on developing a generic alumina and alumina-silica based ceramic waste form capable of immobilizing any nuclear waste with a high aluminum content. Such wastes include the Savannah River Plant wastes, Hanford neutralized purex wastes, and Hanford N-Reactor acid wastes. The design approach and process technology in the two reports demonstrate how the generic high waste loaded ceramic form can be applied to a broad range of nuclear waste compositions. The individual sections are abstracted and indexed separately.

  7. The field treatment of the nuclear spectrum. Historical foundation and two contributions to its ensuing development

    Science.gov (United States)

    Bes, Daniel R.

    2016-06-01

    The highlights of the model which was developed during the 1950s at the Niels Bohr Institute, Copenhagen, under the leadership of Aage Bohr and Ben Mottelson, are described in this contribution. Subsequently, it is shown that the field concept—the fundamental tool of the unified model—is not only an intelligent guess to describe the difficult many-body nuclear system. By means of a systematic expansion of field-coupling effects, the nuclear field theory (NFT) accounts for the overcompleteness of the initial product basis and the overlooking of the Pauli principle acting between constituents of the basis. Eventually it leads to the exact solution of the nuclear many-body problem. The description in terms of fields involves another problem if the field violates a symmetry inherent to the initial problem. The solution is borrowed from the BRST treatments of gauge systems, in which the lost symmetry is replaced by a more powerful one.

  8. Development of a software platform for providing environmental monitoring data for the Fukushima Daiichi nuclear accident.

    Science.gov (United States)

    Seki, A; Saito, O; Nago, H; Suzuki, K; Tomishima, K; Saito, K; Takemiya, H

    2015-04-01

    In nuclear emergencies, it is especially important to carry out a wide range of environmental monitoring and provide the data immediately so as to understand the current distribution of radionuclides and investigate countermeasures. Therefore, it is indispensable for a nuclear emergency response to establish a system that supports rapid provision of these data. The authors have been developing the software platform by integrating technologies of environmental monitoring, information processing and network communication, based on the experience of the Fukushima Daiichi Nuclear Accident. It was discovered that the platform is effective in reducing the time needed to publish the monitoring data. Reducing the cost and workload for publishing the monitoring data is also important because monitoring should be continued over a few decades in the case of the Fukushima accident. The authors' platform is expected to help to mitigate the problem, too.

  9. Development of nuclear power and impacts on public safety and security

    Energy Technology Data Exchange (ETDEWEB)

    Bochmann, H.P.

    1985-07-01

    The author summarizes the contribution of nuclear power to the overall power supply in the FRG, impacts of the nuclear power industry on public safety and security, and the legal instruments available to protect the public. He concludes his discussion of facts and arguments with the following statements: protection against interference or any other harmful actions of third parties aimed against nuclear installations must be devised so as to practically guarantee prevention of sabotage or any acts of terrorism. Preventive measures have to be made with an eye to what is sensible in practice, as perfectionism might have the adverse effect. The available concept of integrated protection and engineered safety, which has been set up in 1977, will be a sufficient means of reacting to near developments and information in a flexible and effective manner.

  10. Role of Halden Reactor Project for world-wide nuclear energy development

    Energy Technology Data Exchange (ETDEWEB)

    McGrath, M.A.; Volkov, B.

    2011-07-01

    The great interest for utilization of nuclear materials to produce energy in the middle of last century needed special investigations using first class research facilities. Common problems in the area of nuclear fuel development motivated the establishment of joint research efforts. The OECD Halden Reactor Project (HRP) is a good example of such a cooperative research effort, which has been performing for more than 50 years. During that time, the Halden Reactor evolved from a prototype heavy water reactor envisaged as a power source for different applications to a research reactor that is able to simulate in-core conditions of modern commercial power reactors. The adaptability of the Halden Reactor enables the HRP to be an important international test facility for nuclear fuels and materials development. The long-term international cooperation is based on the flexible HRP organizational structure which also provides the continued success. [1,2] This paper gives a brief history of the Halden Reactor Project and its contribution to world-wide nuclear energy development. Recent expansion of the Project to the East and Asian countries may also assist and stimulate the development of a nuclear industry within these countries. The achievements of the HRP rely on the versatility of the research carried out in the reactor with reliable testing techniques and in-pile instrumentation. Diversification of scientific activity in the areas of development of alternative energy resources and man-machine technology also provide the HRP with a stable position as one of the leaders in the world scientific community. All of these aspects are described in this paper together with current experimental works, including the investigation of ULBA (Kazakhstan) production fuel in comparison with other world fuel suppliers, as well as other future and prospective plans of the Project.(Author)

  11. U.S. Department of Energy Accident Resistant SiC Clad Nuclear Fuel Development

    Energy Technology Data Exchange (ETDEWEB)

    George W. Griffith

    2011-10-01

    A significant effort is being placed on silicon carbide ceramic matrix composite (SiC CMC) nuclear fuel cladding by Light Water Reactor Sustainability (LWRS) Advanced Light Water Reactor Nuclear Fuels Pathway. The intent of this work is to invest in a high-risk, high-reward technology that can be introduced in a relatively short time. The LWRS goal is to demonstrate successful advanced fuels technology that suitable for commercial development to support nuclear relicensing. Ceramic matrix composites are an established non-nuclear technology that utilizes ceramic fibers embedded in a ceramic matrix. A thin interfacial layer between the fibers and the matrix allows for ductile behavior. The SiC CMC has relatively high strength at high reactor accident temperatures when compared to metallic cladding. SiC also has a very low chemical reactivity and doesn't react exothermically with the reactor cooling water. The radiation behavior of SiC has also been studied extensively as structural fusion system components. The SiC CMC technology is in the early stages of development and will need to mature before confidence in the developed designs can created. The advanced SiC CMC materials do offer the potential for greatly improved safety because of their high temperature strength, chemical stability and reduced hydrogen generation.

  12. Development of Welding and Instrumentation Technology for Nuclear Fuel Test Rod

    Energy Technology Data Exchange (ETDEWEB)

    Joung, Chang Young; Ahn, Sung Ho; Heo, Sung Ho; Hong, Jin Tae; Kim, Ka Hye [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    It is necessary to develop various types of welding, instrumentation and helium gas filling techniques that can conduct TIG spot welding exactly at a pin-hole of the end-cap on the nuclear fuel rod to fill up helium gas. The welding process is one of the most important among the instrumentation processes of the nuclear fuel test rod. To manufacture the nuclear fuel test rod, a precision welding system needs to be fabricated to develop various welding technologies of the fuel test rod jointing the various sensors and end-caps on a fuel cladding tube, which is charged with fuel pellets and component parts. We therefore designed and fabricated an orbital TIG welding system and a laser welding system. This paper describes not only some experiment results from weld tests for the parts of a nuclear fuel test rod, but also the contents for the instrumentation process of the dummy fuel test rod installed with the C-type T. C. A dummy nuclear fuel test rod was successfully fabricated with the welding and instrumentation technologies acquired with various tests. In the test results, the round welding has shown a good weldability at both the orbital TIG welding system and the fiber laser welding system. The spot welding to fill up helium gas has shown a good welding performance at a welding current of 30A, welding time of 0.4 sec and gap of 1 mm in a helium gas atmosphere. The soundness of the nuclear fuel test rod sealed by a mechanical sealing method was confirmed by helium leak tests and microstructural analyses.

  13. Structured system engineering methodologies used to develop a nuclear thermal propulsion engine

    Science.gov (United States)

    Corban, R.; Wagner, R.

    1993-01-01

    To facilitate the development of a space nuclear thermal propulsion engine for manned flights to Mars, requirements must be established early in the technology development cycle. The long lead times for the acquisition of the engine system and nuclear test facilities demands that the engine system size, performance and safety goals be defined at the earliest possible time. These systems are highly complex and require a large multidisciplinary systems engineering team to develop and track requirements, and to ensure that the as-built system reflects the intent of the mission. A methodology has been devised which uses sophisticated computer tools to effectively develop and interpret functional requirements, and furnish these to the specification level for implementation.

  14. Development of NPA4K (Nuclear Plant Analyzer for KALIMER) program

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong Bum; Kim, K. K.; Seo, K. C.; Yoon, J. S.; Hahn, H. D

    2000-05-01

    The NPA4K (nuclear plant analyzer for KALIMER) is developed for the user's convenience to run the SSC-K computer code displaying the safety related parameters simultaneously. Delphi program language is used to develop the program and the program can be run in the PC environment. It consists of KalimerUnit, Read TIUnit, SSCUnit, Choose Unit, GraphUnit, ExtensionUnit and TFieldUnit. Main control is performed in KalimerUnit.

  15. Nuclear safeguards research and development. Program status report, October 1980-January 1981

    Energy Technology Data Exchange (ETDEWEB)

    Henry, C.N. (comp.)

    1981-11-01

    This report presents the status of the Nuclear Safeguards Research and Development Program pursued by the Energy, Chemistry-Materials Science, and Operational Security/Safeguards Divisions of the Los Alamos National Laboratory. Topics include nondestructive assay technology development and applications, international safeguards systems. Also discussed are training courses, technology transfer, analytical chemistry methods for fissionable materials safeguards, the Department of Energy Computer Security Technical Center, and operational security.

  16. Development of an Origin Trace Method based on Bayesian Inference and Artificial Neural Network for Missing or Stolen Nuclear Materials

    Energy Technology Data Exchange (ETDEWEB)

    Bin, Yim Ho; Min, Lee Seung; Min, Kim Kyung; Jeong, Hong Yoon; Kim, Jae Kwang [Nuclear Security Div., Daejeon (Korea, Republic of)

    2014-05-15

    Thus, 'to put nuclear materials under control' is an important issue for prosperity mankind. Unfortunately, numbers of illicit trafficking of nuclear materials have been increased for decades. Consequently, security of nuclear materials is recently spotlighted. After the 2{sup nd} Nuclear Security Summit in Seoul in 2012, the president of Korea had showed his devotion to nuclear security. One of the main responses for nuclear security related interest of Korea was to develop a national nuclear forensic support system. International Atomic Energy Agency (IAEA) published the document of Nuclear Security Series No.2 'Nuclear Forensics Support' in 2006 to encourage international cooperation of all IAEA member states for tracking nuclear attributions. There are two main questions related to nuclear forensics to answer in the document. The first question is 'what type of material is it?', and the second one is 'where did the material come from?' Korea Nuclear Forensic Library (K-NFL) and mathematical methods to trace origins of missing or stolen nuclear materials (MSNMs) are being developed by Korea Institute of Nuclear Non-proliferation and Control (KINAC) to answer those questions. Although the K-NFL has been designed to perform many functions, K-NFL is being developed to effectively trace the origin of MSNMs and tested to validate suitability of trace methods. New fuels and spent fuels need each trace method because of the different nature of data acquisition. An inductive logic was found to be appropriate for new fuels, which had values as well as a bistable property. On the other hand, machine learning was suitable for spent fuels, which were unable to measure, and thus needed simulation.

  17. Changes in the nuclear proteome of developing wheat (Triticum aestivum L.) grain

    Science.gov (United States)

    Bonnot, Titouan; Bancel, Emmanuelle; Chambon, Christophe; Boudet, Julie; Branlard, Gérard; Martre, Pierre

    2015-01-01

    Wheat grain end-use value is determined by complex molecular interactions that occur during grain development, including those in the cell nucleus. However, our knowledge of how the nuclear proteome changes during grain development is limited. Here, we analyzed nuclear proteins of developing wheat grains collected during the cellularization, effective grain-filling, and maturation phases of development, respectively. Nuclear proteins were extracted and separated by two-dimensional gel electrophoresis. Image analysis revealed 371 and 299 reproducible spots in gels with first dimension separation along pH 4–7 and pH 6–11 isoelectric gradients, respectively. The relative abundance of 464 (67%) protein spots changed during grain development. Abundance profiles of these proteins clustered in six groups associated with the major phases and phase transitions of grain development. Using nano liquid chromatography-tandem mass spectrometry to analyse 387 variant and non-variant protein spots, 114 different proteins were identified that were classified into 16 functional classes. We noted that some proteins involved in the regulation of transcription, like HMG1/2-like protein and histone deacetylase HDAC2, were most abundant before the phase transition from cellularization to grain-filling, suggesting that major transcriptional changes occur during this key developmental phase. The maturation period was characterized by high relative abundance of proteins involved in ribosome biogenesis. Data are available via ProteomeXchange with identifier PXD002999. PMID:26579155

  18. A summary of the 2nd workshop on Human Resources Development (HRD) in the nuclear field in Asia. FY2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-06-01

    The Human Resources Development (HRD) Project was added in 1999 as a Cooperation Activity of 'the Forum for Nuclear Cooperation in Asia (FNCA)' which is organized by Nuclear Committee. The HRD Project supports to solidify the foundation of nuclear development utilization in Asia by promoting human resources development in Asian countries. The principal activity of the HRD Project is to hold the Workshop on Human Resources Development in the Nuclear Field in Asia once a year. The objective of the Workshop is to clarify problems and needs of the human resources development of each country and to support it mutually by exchanging information etc. The report consists of a summary of the 2nd Workshop on Human Resources Development in the Nuclear Field in Asia held on November 27 and 28, 2000 at Tokai Research Establishment of JAERI. (author)

  19. Development of reliability-based safety enhancement technology; development of organization concept model in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Chang Hyun; Kim, Ju Youl; Kim, Yoon Ik; Yang, Hui Chang; Lee, Yong Sik; Kim, Se Hyung [Seoul National University, Seoul (Korea)

    2002-03-01

    The influences of organizational factors on safety of nuclear power plants are mentioned in the early 1970s and noticed after being focused on in the accident report of TMI in 1979. These needs let us implement this research and the purposes of this research are to assess the organizational influences and to develop the organizational conceptual model to establish the basis of identifying the organizational factors, using this model to contribute to enhance safety and economics in nuclear power plants. Eventually research on the organizational influences is expected to have two effects, which are to improve safety through identifying potential causes of accidents and to elevate economics as a new approach to more efficient operation of nuclear power plants. In this study, recent studies were surveyed on the organizational conceptual model, the identification of organizational factors, assessment of organizational influences and evaluation methods of organizational factors and organizational influences among the overseas and domestic researches. In addition specific characteristics of domestic nuclear power plants were tried to identify through plant visit and an evaluation method of organizational influences on component maintenance and human performance were developed and presented. 71 refs., 40 figs., 18 tabs. (Author)

  20. Developing a taxonomy of coordination behaviours in nuclear power plant control rooms during emergencies.

    Science.gov (United States)

    Wang, Dunxing; Gao, Qin; Li, Zhizhong; Song, Fei; Ma, Liang

    2017-05-19

    This study aims to develop a taxonomy of coordination behaviours during emergencies in nuclear power plants (NPPs). We summarised basic coordination behaviours from literature in aviation, health care and nuclear field and identified coordination behaviours specific to the nuclear domain by interviewing and surveying control crew operators. The established taxonomy includes 7 workflow stages and 24 basic coordination behaviours. To evaluate the reliability and feasibility of the taxonomy, we analysed 12 videos of operators' training sessions by coding coordination behaviours with the taxonomy and the inter-rater reliability was acceptable. Further analysis of the frequency, the duration and the direction of the coordination behaviours revealed four coordination problems. This taxonomy provides a foundation of systematic observation of coordination behaviours among NPP crews, advances researchers' understanding of the coordination mechanism during emergencies in NPPs and facilitate the possibility to deepen the understanding of the relationships between coordination behaviours and team performance. Practitioner Summary: A taxonomy of coordination behaviours during emergencies in nuclear power plants was developed. Reliability and feasibility of the taxonomy was verified through the analysis of 12 training sessions. The taxonomy can serve as an observation system for analysis of coordination behaviours and help to identify coordination problems of control crews.

  1. Developing a Computerized Aging Management System for Concrete Structures in Finnish Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Hradil P.

    2013-07-01

    Full Text Available Finland has four nuclear reactors units in two power plants. The first unit started operation in 1977 and in the early 1980's all four units were in use. During the last few years the aging management of the Nuclear Power Plant's (NPP concrete structures has grown an important issue because the existing structures are reaching the end of their licensed operating lifetime (about 40 years. Therefore the nuclear power companies are developing aging management systems to avoid premature degradation of NPP facilities and to be able to extend their operating lifetime. This paper is about the development of a computerized ageing management system for the nuclear power plants concrete structures. The computerized ageing management system is built upon central database and implementation applications. It will assist the personnel of power companies to implement the aging management activities at different phases of the lifetime of a power plant. It will provide systematic methods for planning, surveillance, inspection, monitoring, condition assessment, maintenance and repair of structures.

  2. Developing a Computerized Aging Management System for Concrete Structures in Finnish Nuclear Power Plants

    Science.gov (United States)

    Al-Neshawy, F.; Piironen, J.; Sistonen, E.; Vesikari, E.; Tuomisto, M.; Hradil, P.; Ferreira, M.

    2013-07-01

    Finland has four nuclear reactors units in two power plants. The first unit started operation in 1977 and in the early 1980's all four units were in use. During the last few years the aging management of the Nuclear Power Plant's (NPP) concrete structures has grown an important issue because the existing structures are reaching the end of their licensed operating lifetime (about 40 years). Therefore the nuclear power companies are developing aging management systems to avoid premature degradation of NPP facilities and to be able to extend their operating lifetime. This paper is about the development of a computerized ageing management system for the nuclear power plants concrete structures. The computerized ageing management system is built upon central database and implementation applications. It will assist the personnel of power companies to implement the aging management activities at different phases of the lifetime of a power plant. It will provide systematic methods for planning, surveillance, inspection, monitoring, condition assessment, maintenance and repair of structures.

  3. Nuclear Chemistry.

    Science.gov (United States)

    Chemical and Engineering News, 1979

    1979-01-01

    Provides a brief review of the latest developments in nuclear chemistry. Nuclear research today is directed toward increased activity in radiopharmaceuticals and formation of new isotopes by high-energy, heavy-ion collisions. (Author/BB)

  4. Development of ion beam techniques for the study of special nuclear materials related problems

    Energy Technology Data Exchange (ETDEWEB)

    Maggiore, C.J.; Tesmer, J.R.; Martz, J.C. [and others

    1998-11-01

    This is the final report of a three-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). The scientific objective of this project was to develop the ion beam techniques for the characterization of actinides and their effects on other materials. It was designed to enhance their ability to quantitatively understand the oxidation, corrosion, diffusion, stability, and radiation damage of actinides and the materials with which they are in contact. The authors developed and applied several low-energy nuclear techniques (resonant and nonresonant backscattering, nuclear reaction analysis, and particle-induced x-ray emission) to the quantitative study of the near surfaces of actinide and tritide materials, and determined the absolute accuracy and precision of ion beam measurements on these materials. They also demonstrated the use of variable-energy alpha beams for the study of accelerated aging of polymeric materials in contact with actinide materials.

  5. Development of knowledge acquisition methods for knowledge base construction for autonomous nuclear plant

    Energy Technology Data Exchange (ETDEWEB)

    Sasajima, M.; Kitamura, Y.; Mizoguchi, R. [Osaka Univ., Ibaraki (Japan). Inst. of Scientific and Industrial Research; Yoshikawa, S.

    1994-03-01

    This report describes a development of an ontology for computerized representation of behaviors and functions of number power plants. This ontology also enables computers to predict plant behaviors under assumed changes of boundary conditions and to derive cause identification suggestions of observed anomalies, as well as to represent functions and behaviors. Technical requirements in this development were recognized as clarified distinguishment of functions from behaviors and efficient plant behavior reasoning, and these have been successfully attained. The purpose of this development is to achieve knowledge sharing between human and automized instrumentation and control system about nuclear plant functions and behaviors, to realize cooperation of human and automized system for safe and cost acceptable nuclear plant operation. (author)

  6. Feasibility of AEDC test facility support for nuclear thermal propulsion system development

    Science.gov (United States)

    Roler, Max A.; Turner, Eugene E.; Bradley, Dale

    1993-06-01

    Test facility requirements to support the development of nuclear propulsion have been evaluated and shortfalls within current test facility capabilities identified. The development of a nonnuclear heat source capable of heating the high-pressure, high mass flowrate hydrogen propellant to the required operating temperature has been identified as a key enabling technology. Other significant issues identified were the safety aspects associated with the cooling, pumping, and disposal of the hot hydrogen exhaust gas. The rocket test facilities at the U.S. Air Force Arnold Engineering Development Center (AEDC) were evaluated to determine the ability to support the operationally realistic testing of 'nonirradiated' nuclear propulsion components and/or subassemblies under simulated altitude conditions. An overview of the results from this evaluation process is presented herein.

  7. Feasibility of AEDC test facility support for nuclear thermal propulsion system development

    Energy Technology Data Exchange (ETDEWEB)

    Roler, M.A.; Turner, E.E.; Bradley, D.

    1993-06-01

    Test facility requirements to support the development of nuclear propulsion have been evaluated and shortfalls within current test facility capabilities identified. The development of a nonnuclear heat source capable of heating the high-pressure, high mass flowrate hydrogen propellant to the required operating temperature has been identified as a key enabling technology. Other significant issues identified were the safety aspects associated with the cooling, pumping, and disposal of the hot hydrogen exhaust gas. The rocket test facilities at the U.S. Air Force Arnold Engineering Development Center (AEDC) were evaluated to determine the ability to support the operationally realistic testing of 'nonirradiated' nuclear propulsion components and/or subassemblies under simulated altitude conditions. An overview of the results from this evaluation process is presented herein. 3 refs.

  8. Development and Operation of International Nuclear Education/Training Program and HRD Cooperation Network

    Energy Technology Data Exchange (ETDEWEB)

    Lee, E. J.; Min, B. J.; Han, K. W. (and others)

    2006-12-15

    The primary result of the project is the establishment of a concept of International Nuclear R and D Academy that integrates the on-going long term activity for international nuclear education/training and a new activity to establish an international cooperation network for nuclear human resources development. For this, the 2007 WNU Summer Institute was hosted with the establishment of an MOU and subsequent preparations. Also, ANENT was promoted through development of a cyber platform for the ANENT web-portal, hosting the third ANENT Coordination Committee meeting, etc. Then a cooperation with universities in Vietnam was launched resulting in preparation of an MOU for the cooperation. Finally, a relevant system framework was established and required procedures were drafted especially for providing students from developing countries with long term education/training programs (e.g. MS and Ph D. courses). The international nuclear education/training programs have offered 13 courses to 182 people from 43 countries. The overall performance of the courses was evaluated to be outstanding. In parallel, the establishment of an MOU for the cooperation of KOICA-IAEA-KAERI courses to ensure their stable and systematic operation. Also, an effort was made to participate in FNCA. Atopia Hall of the International Nuclear Training and Education Center (INTEC) hosted 477 events (corresponding to 18,521 participants) and Nuri Hall (guesthouse) accommodated 4,616 people in 2006. This shows a steady increase of the use rate since the opening of the center, along with a continuous improvement of the equipment.

  9. Development of interspecies nuclear transfer embryos reconstructed with argali (Ovis ammon) somatic cells and sheep ooplasm.

    Science.gov (United States)

    Pan, Xiaoyan; Zhang, Yanli; Guo, Zhiqin; Wang, Feng

    2014-02-01

    Interspecies nuclear transfer has already achieved success in several species, which shows great potential in recovery and conservation of endangered animals. The study was conducted to establish an efficient system for in vitro argali (Ovis ammon)-sheep embryo reconstruction via interspecies somatic cell nuclear transfer (iSCNT). The competence of domestic sheep cytoplasts to reprogram the adult argali fibroblast nuclei was evaluated, and the effects of enucleation methods and donor cell passage and cell state on the in vitro development of argali-sheep cloned embryos were also examined. Sheep oocytes could support argali and sheep fibroblast cell nuclei transfer and develop to blastocysts in vitro. Oocytes matured for 21–23 h and enucleated by chemically assisted enucleation (CAE) had a higher enucleation rate than blind enucleation (BE), but the development rate of iSCNTembryos was the same (P>0.05). Moreover, passage numbers of fibroblast cells cell cycle stages did not affect the development rate of iSCNT reconstructed embryos. Thus sheep cytoplasm successfully supports argali nucleus development to blastocyst stage after optimising the nuclear transfer procedure, which indicates that iSCNT can be used to conserve endangered argali in the near future.

  10. User input verification and test driven development in the NJOY21 nuclear data processing code

    Energy Technology Data Exchange (ETDEWEB)

    Trainer, Amelia Jo [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Conlin, Jeremy Lloyd [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); McCartney, Austin Paul [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-08-21

    Before physically-meaningful data can be used in nuclear simulation codes, the data must be interpreted and manipulated by a nuclear data processing code so as to extract the relevant quantities (e.g. cross sections and angular distributions). Perhaps the most popular and widely-trusted of these processing codes is NJOY, which has been developed and improved over the course of 10 major releases since its creation at Los Alamos National Laboratory in the mid-1970’s. The current phase of NJOY development is the creation of NJOY21, which will be a vast improvement from its predecessor, NJOY2016. Designed to be fast, intuitive, accessible, and capable of handling both established and modern formats of nuclear data, NJOY21 will address many issues that many NJOY users face, while remaining functional for those who prefer the existing format. Although early in its development, NJOY21 is quickly providing input validation to check user input. By providing rapid and helpful responses to users while writing input files, NJOY21 will prove to be more intuitive and easy to use than any of its predecessors. Furthermore, during its development, NJOY21 is subject to regular testing, such that its test coverage must strictly increase with the addition of any production code. This thorough testing will allow developers and NJOY users to establish confidence in NJOY21 as it gains functionality. This document serves as a discussion regarding the current state input checking and testing practices of NJOY21.

  11. Accelerated development of Zr-containing new generation ferritic steels for advanced nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Tan, Lizhen [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Yang, Ying [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Sridharan, K. [Univ. of Wisconsin, Madison, WI (United States)

    2015-12-01

    The mission of the Nuclear Energy Enabling Technologies (NEET) program is to develop crosscutting technologies for nuclear energy applications. Advanced structural materials with superior performance at elevated temperatures are always desired for nuclear reactors, which can improve reactor economics, safety margins, and design flexibility. They benefit not only new reactors, including advanced light water reactors (LWRs) and fast reactors such as the sodium-cooled fast reactor (SFR) that is primarily designed for management of high-level wastes, but also life extension of the existing fleet when component exchange is needed. Developing and utilizing the modern materials science tools (experimental, theoretical, and computational tools) is an important path to more efficient alloy development and process optimization. The ultimate goal of this project is, with the aid of computational modeling tools, to accelerate the development of Zr-bearing ferritic alloys that can be fabricated using conventional steelmaking methods. The new alloys are expected to have superior high-temperature creep performance and excellent radiation resistance as compared to Grade 91. The designed alloys were fabricated using arc-melting and drop-casting, followed by hot rolling and conventional heat treatments. Comprehensive experimental studies have been conducted on the developed alloys to evaluate their hardness, tensile properties, creep resistance, Charpy impact toughness, and aging resistance, as well as resistance to proton and heavy ion (Fe2+) irradiation.

  12. Study on Model for Human Resources Development Strategy in the Nuclear Field

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Eui Jin [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2005-07-01

    Qualified manpower is an essential for the successful implementation of a national long-term nuclear development program as well as the associated R and D programs. Such manpower could only be developed systematically under a well-established national model and strategy, which addresses the demand for human resources, number of personnel and timing, and the education and training. To discuss a model for human resources development, it is suggested to consider the following: approach to the Human Resources Development (HRD) Model, HRD policy targets, estimation of the manpower requirement, organizational coordination frameworks for the HRD, promotion of HRD in the action plan.

  13. Development of Nuclear Magnetic Resonance Imaging/spectroscopy for improved petroleum recovery. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Barrufet, M.A.; Flumerfelt, F.W.; Walsh, M.P.; Watson, A.T.

    1994-04-01

    The overall objectives of this program are to develop and apply Nuclear Magnetic Resonance Imaging (NMRI) and CT X-Ray Scanning methods for determining rock, fluid, and petrophysical properties and for fundamental studies of multiphase flow behavior in porous media. Specific objectives are divided into four subtasks: (1) development of NMRI and CT scanning for the determination of rock-fluid and petrophysical properties; (2) development of NMRI and CT scanning for characterizing conventional multiphase displacement processes; (3) development of NMR and CT scanning for characterizing dispersed phase processes; and (4) miscible displacement studies.

  14. Development of Nuclear Magnetic Resonance Imaging/spectroscopy for improved petroleum recovery. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Barrufet, M.A.; Flumerfelt, F.W.; Walsh, M.P.; Watson, A.T.

    1994-04-01

    The overall objectives of this program are to develop and apply Nuclear Magnetic Resonance Imaging (NMRI) and CT X-Ray Scanning methods for determining rock, fluid, and petrophysical properties and for fundamental studies of multiphase flow behavior in porous media. Specific objectives are divided into four subtasks: (1) development of NMRI and CT scanning for the determination of rock-fluid and petrophysical properties; (2) development of NMRI and CT scanning for characterizing conventional multiphase displacement processes; (3) development of NMR and CT scanning for characterizing dispersed phase processes; and (4) miscible displacement studies.

  15. Action research for the development of the organizational climate in nuclear power plants. Review of the 6-year research and development program

    Energy Technology Data Exchange (ETDEWEB)

    Yoshida, Michio [Kumamoto Univ. (Japan). Faculty of Education; Misumi, Jyuji; Misumi, Emiko; Kotani, Fumio; Fukui, Hirokazu; Sakurai, Yukihiro

    1998-09-01

    The Institute of Nuclear Safety System, Incorporated and the Japan Institute for Group Dynamics have conducted action research for the development of the organizational climate in nuclear power plants. First, two types of scales were completed. One is for measuring the leadership behavior of leaders working at nuclear power plants and the other is for measuring the safety consciousness of workers. After having diagnosed the reality of actual nuclear power plants using those scales developed, leadership training courses were developed and implemented successfully. Analyses of the commitment to organization and self-efficacy and the relationship between leadership and personality were conducted as well. (author)

  16. Development of CANDU advanced fuel fabrication technology - A development of amorphous alloys for the solder of nuclear reactor materials

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jai Young; Lee, Ki Young; Kim, Yoon Kee; Jung, Jae Han; Yu, Ji Sang; Kim, Hae Yeol; Han, Young Su [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    1996-07-01

    In the case of advanced CANDU fuel being useful in future, the fabrication processes for soundness insurance of a improved nuclear fuel bundle must be developed at the same time because it have three times combustibility as existing fuel. In particular, as the improved nuclear fuel bundle in which a coated layer thickness is thinner than existing that, firmity of a joint part is very important. Therefore, we need to develop a joint technique using new solder which can settle a potential problem in current joining method. As the Zr-Be alloy system and the Ti-Be system are composed with the elements having high neutron permeability, they are suitable for joint of nuclear fuel pack. The various compositions Zr-Be and Ti-Be binary metallic glass alloys were applicable to the joining the nuclear fuel bundles. The thickness of joint layer using the Zr{sub 1-x} Be{sub x} amorphous ribbon as a solder is thinner than that using physical vapor deposited Be. Among the Zr{sub 1-x} Be{sub x} amorphous binary alloys, Zr{sub 0.7} Be{sub 0.3} binary alloy is the most appropriated for joint of nuclear fuel bundle because its joint layer is smooth and thin due to low degree of Be diffusion. The microstructures of brazed layer using Ti{sub 1-y} Be{sub y} alloy, however, a solid-solution layer composed with Zr and Ti is formed toward the Zr cladding sheath and many of Zr is detected in the joint lever. 20 refs., 8 tabs., 23 figs. (author)

  17. ORNL Nuclear Safety Research and Development Program Bimonthly Report for July-August 1968

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W.B.

    2001-08-17

    The accomplishments during the months of July and August in the research and development program under way at ORNL as part of the U.S. Atomic Energy Commission's Nuclear Safety Program are summarized, Included in this report are work on various chemical reactions, as well as the release, characterization, and transport of fission products in containment systems under various accident conditions and on problems associated with the removal of these fission products from gas streams. Although most of this work is in general support of water-cooled power reactor technology, including LOFT and CSE programs, the work reflects the current safety problems, such as measurements of the prompt fuel element failure phenomena and the efficacy of containment spray and pool-suppression systems for fission-product removal. Several projects are also conducted in support of the high-temperature gas-cooled reactor (HTGR). Other major projects include fuel-transport safety investigations, a series of discussion papers on various aspects of water-reactor technology, antiseismic design of nuclear facilities, and studies of primary piping and steel, pressure-vessel technology. Experimental work relative to pressure-vessel technology includes investigations of the attachment of nozzles to shells and the implementation of joint AEX-PVFX programs on heavy-section steel technology and nuclear piping, pumps, and valves. Several of the projects are directly related to another major undertaking; namely, the AEC's standards program, which entails development of engineering safeguards and the establishment of codes and standards for government-owned or -sponsored reactor facilities. Another task, CHORD-S, is concerned with the establishment of computer programs for the evaluation of reactor design data, The recent activities of the NSIC and the Nuclear Safety journal in behalf of the nuclear community are also discussed.

  18. Development of Amorphous Filler Alloys for the Joining of Nuclear Materials

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jai Young; Kim, Dong Myong; Kang, Yoon Sun; Jung, Jae Han; Yu, Ji Sang; Kim, Hae Yeol; Lee, Ho [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    1997-08-01

    In the case of advanced CANDU fuel being useful in future, the fabrication processes for soundness insurance of a improved nuclear fuel bundle must be developed at the same time because it have three times combustibility as existing fuel. In particular, as the improved nuclear fuel bundle in which a coated layer thickness is thinner than existing that, firmity of a joint part is very important. Therefore, we need to develop a joint technique using new solder which can settle a potential problem in current joining method. As the Zr-Be alloy system is composed with the elements having high neutron permeability, they are suitable for joint of nuclear fuel pack. The various compositions Zr-Be binary metallic glass alloys were applicable to the joining the nuclear fuel bundles. The thickness of joint layer using the Zr{sub 1}-{sub x}Be{sub x} amorphous ribbon as a solder is thinner than that using physical vapor deposited Be. Among the Zr{sub 1}-{sub x}Be{sub x} amorphous binary alloys, Zr{sub 0}.7Be-0.3 binary alloy is the most appropriate for joint of nuclear fuel bundle because its joint layer is smooth and thin due to low degree of Be diffusion. In the case of the Zr{sub (}0.7-y)Ti{sub y}Be{sub 0}.3 and Zr{sub (}0.7-y)Nb{sub y}Be{sub 0}3 ternary amorphous alloys, the crystallization temperature(T{sub x}) and activation energy(E{sub x}) increase as the contents of Nb and Ti increase respectively. In the aspect of thermal stability, the ternary amorphous alloys are superior than Zr-Be binary amorphous alloys and Zr-Ti-Be amorphous alloy is superior than Zr-Nb-Be amorphous alloy. 12 refs., 5 tabs., 25 figs. (author)

  19. Nuclear physics with laser-electron-photons. Developments and perspectives at SPring-8

    Energy Technology Data Exchange (ETDEWEB)

    Fujiwara, Mamoru [Osaka Univ., Ibaraki (Japan). Research Center for Nuclear Physics

    1998-03-01

    By the Compton scattering with ultraviolet laser beam using the 8 GeV electron beam of the SPring-8, the photon beam which is polarized by nearly 100% is obtained in 1-3.5 GeV region. The quark nuclear physics research at this facility is unique in the world, and it is expected that in the experiment at the SPring-8, the collision phenomena of polarized, high energy gamma-ray and the quarks in nucleons and the knockout phenomena of quarks are observed. Also the polarization experiment for clarifying ``the origin of nucleon spin`` has been proposed. Japan can stand at the top in the world in the research of quark nuclear physics with leptons. In the inverse Compton scattering using far infrared laser, the gamma-ray with good directionality of MeV range is obtained, and it will be applied widely to the research on E1 resonance and M1 excitation of atomic nuclei. In this report, the medium energy quark nuclear physics developed at the SPring-8 is outlined, and the nuclear physics which is expected to be developed when the high intensity, high polarization gamma-ray of about 10 MeV is generated is discussed. The detection of s, anti-s components in nucleons, research on baryon deformation and baryon spectra, verification of the Gerasimov, Drell-Hearn law of sum, meson structure, test of quark model by the photolysis of deuterons, dual Ginzburg Landau theory exploration, research on the mass and behavior of mesons in nuclear media are discussed. (K.I.)

  20. Nuclear physics with laser-electron-photons. Developments and perspectives at SPring-8

    Energy Technology Data Exchange (ETDEWEB)

    Fujiwara, Mamoru [Osaka Univ., Ibaraki (Japan). Research Center for Nuclear Physics

    1998-03-01

    By the Compton scattering with ultraviolet laser beam using the 8 GeV electron beam of the SPring-8, the photon beam which is polarized by nearly 100% is obtained in 1-3.5 GeV region. The quark nuclear physics research at this facility is unique in the world, and it is expected that in the experiment at the SPring-8, the collision phenomena of polarized, high energy gamma-ray and the quarks in nucleons and the knockout phenomena of quarks are observed. Also the polarization experiment for clarifying ``the origin of nucleon spin`` has been proposed. Japan can stand at the top in the world in the research of quark nuclear physics with leptons. In the inverse Compton scattering using far infrared laser, the gamma-ray with good directionality of MeV range is obtained, and it will be applied widely to the research on E1 resonance and M1 excitation of atomic nuclei. In this report, the medium energy quark nuclear physics developed at the SPring-8 is outlined, and the nuclear physics which is expected to be developed when the high intensity, high polarization gamma-ray of about 10 MeV is generated is discussed. The detection of s, anti-s components in nucleons, research on baryon deformation and baryon spectra, verification of the Gerasimov, Drell-Hearn law of sum, meson structure, test of quark model by the photolysis of deuterons, dual Ginzburg Landau theory exploration, research on the mass and behavior of mesons in nuclear media are discussed. (K.I.)

  1. The development of mobile robot for security application and nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kim, B. S.; Lee, Y. B.; Choi, Y. S.; Seo, Y. C.; Park, Y. M

    1999-12-01

    The use of a mobile robot system in nuclear radioactive environments has the advantage of watching and inspecting the NPP safety-related equipment systematically and repairing damaged parts efficiently, thereby enhancing the safe operations of NPPs as well as reducing significantly personnel's dose rate to radioactive environment. Key technology achieved through the development of such robotic system can be used for security application and can offer new approaches to many of the tasks faced to the industry as well. The mobile robot system was composed of a mobile subsystem, a manipulator subsystem, a control subsystem, and a sensor subsystem to use in security application and nuclear radioactive environments. The mobile subsystem was adopted to synchro-drive method to improve the mobility of it. And the manipulator subsystem was developed to minimize the weight and easy to control at remote site. Finally, we developed the USB-based robot control system considering the expandability and modularity. The developed mobile robot for inspection and security was experimented for the collision avoidance and autonomous algorithm, and then it was confirmed that the mobile robot was very effective to the security application and inspection of nuclear facilities. (author)

  2. Condition monitoring requirements for the development of a space nuclear propulsion module

    Science.gov (United States)

    Wagner, Robert C.

    1993-01-01

    To facilitate the development of a space nuclear propulsion module for manned flights to Mars, requirements must be established early in the technology cycle. The long lead times for the acquisition of the engine system and nuclear test facilities demands that the engine system, size, performance, safety goals and condition monitoring philosophy be defined at the earliest possible time. These systems are highly complex and require a large multi-disciplinary systems engineering team to develop and track the requirements and to ensure that the as-built system reflects the intent of the mission. An effective methodology has been devised coupled with sophisticated computer tools to effectivly develop and interpret the functional requirements. These requirements can then be decomposed down to the specification level for implementation. This paper discusses the application of the methodology and the analyses to develop condition monitoring requirements under a contract with the National Aeronautics and Space Administration (NASA) Lewis Research Center (LeRC) Nuclear Propulsion Office (NPO).

  3. Nuclear control

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Wan Kee [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-02-01

    International cooperation in nuclear industries requires nuclear control as prerequisites. The concept of nuclear control is based on the Treaty on the Non-proliferation of Nuclear Weapon (NPT). The International Atomic Energy Agency (IAEA) plays central role in implementing nuclear control. Nuclear control consists of nuclear safeguards, physical protection, and export/import control. Each member state of NPT is subject to the IAEA`s safeguards by concluding safeguards agreements with the IAEA. IAEA recommends member states to implement physical protection on nuclear materials by `The Physical Protection of Nuclear Material` and `The Convention on the Physical Protection of Nuclear Material` of IAEA. Export/Import Control is to deter development of nuclear weapons by controlling international trade on nuclear materials, nuclear equipments and technology. Current status of domestic and foreign nuclear control implementation including recent induction of national inspection system in Korea is described and functions of recently set-up Technology Center for Nuclear Control (TCNC) under the Korea Atomic Energy Research Institute (KAERI) are also explained. 6 tabs., 11 refs. (Author).

  4. Development of porcine tetraploid somatic cell nuclear transfer embryos is influenced by oocyte nuclei.

    Science.gov (United States)

    Fu, Bo; Liu, Di; Ma, Hong; Guo, Zhen-Hua; Wang, Liang; Li, Zhong-Qiu; Peng, Fu-Gang; Bai, Jing

    2016-02-01

    Cloning efficiency in mammalian systems remains low because reprogramming of donor cells is frequently incomplete. Nuclear factors in the oocyte are removed by enucleation, and this removal may adversely affect reprogramming efficiency. Here, we investigated the role of porcine oocyte nuclear factors during reprogramming. We introduced somatic cell nuclei into intact MII oocytes to establish tetraploid somatic cell nuclear transfer (SCNT) embryos containing both somatic nuclei and oocyte nuclei. We then examined the influence of the oocyte nucleus on tetraploid SCNT embryo development by assessing characteristics including pronucleus formation, cleavage rate, and blastocyst formation. Overall, tetraploid SCNT embryos have a higher developmental competence than do standard diploid SCNT embryos. Therefore, we have established an embryonic model in which a fetal fibroblast nucleus and an oocyte metaphase II plate coexist. Tetraploid SCNT represents a new research platform that is potentially useful for examining interactions between donor nuclei and oocyte nuclei. This platform should facilitate further understanding of the roles played by nuclear factors during reprogramming.

  5. Instrumentation and control developments in the Los Alamos nuclear test program

    Energy Technology Data Exchange (ETDEWEB)

    Perea, J.A.

    1988-01-01

    The United States Department of Energy contracts the Los Alamos National Laboratory to carry out a Nuclear Weapons Test Program in support of the national defense. The program is one of ongoing research to design, build, and test prototype nuclear devices. The goal is to determine what should ultimately be incorporated into the nation's nuclear defense stockpile. All nuclear tests are conducted underground at the Nevada Test Site (NTS). This paper describes the instrumentation and control techniques used by Los Alamos to carry out the tests. Specifically, the contrast between historical methods and new, computer-based technology are discussed. Previous techniques required large numbers of expensive, heavy hardwire cables extending from the surface to the diagnostics rack at the bottom of the vertical shaft. These cables, which provided singular control/monitor functions, have been replaced by a few optical fibers and power cables. This significant savings has been enabled through the adaptation of industrial process control technology using programmable computer control and distributed input/output. Finally, an ongoing process of developing and applying the most suitable instrumentation and control technology to the unique requirements of the Test Program is discussed. 2 refs.

  6. Development of RadRob15, A Robot for Detecting Radioactive Contamination in Nuclear Medicine Departments

    Directory of Open Access Journals (Sweden)

    Shafe A.

    2016-09-01

    Full Text Available Accidental or intentional release of radioactive materials into the living or working environment may cause radioactive contamination. In nuclear medicine departments, radioactive contamination is usually due to radionuclides which emit high energy gamma photons and particles. These radionuclides have a broad range of energies and penetration capabilities. Rapid detection of radioactive contamination is very important for efficient removing of the contamination without spreading the radionuclides. A quick scan of the contaminated area helps health physicists locate the contaminated area and assess the level of activity. Studies performed in IR Iran shows that in some nuclear medicine departments, areas with relatively high levels of activity can be found. The highest contamination level was detected in corridors which are usually used by patients. To monitor radioactive contamination in nuclear medicine departments, RadRob15, a contamination detecting robot was developed in the Ionizing and Non-ionizing Radiation Protection Research Center (INIRPRC. The motor vehicle scanner and the gas radiation detector are the main components of this robot. The detection limit of this robot has enabled it to detect low levels of radioactive contamination. Our preliminary tests show that RadRob15 can be easily used in nuclear medicine departments as a device for quick surveys which identifies the presence or absence of radioactive contamination.

  7. Development of RadRob15, A Robot for Detecting Radioactive Contamination in Nuclear Medicine Departments.

    Science.gov (United States)

    Shafe, A; Mortazavi, S M J; Joharnia, A; Safaeyan, Gh H

    2016-09-01

    Accidental or intentional release of radioactive materials into the living or working environment may cause radioactive contamination. In nuclear medicine departments, radioactive contamination is usually due to radionuclides which emit high energy gamma photons and particles. These radionuclides have a broad range of energies and penetration capabilities. Rapid detection of radioactive contamination is very important for efficient removing of the contamination without spreading the radionuclides. A quick scan of the contaminated area helps health physicists locate the contaminated area and assess the level of activity. Studies performed in IR Iran shows that in some nuclear medicine departments, areas with relatively high levels of activity can be found. The highest contamination level was detected in corridors which are usually used by patients. To monitor radioactive contamination in nuclear medicine departments, RadRob15, a contamination detecting robot was developed in the Ionizing and Non-ionizing Radiation Protection Research Center (INIRPRC). The motor vehicle scanner and the gas radiation detector are the main components of this robot. The detection limit of this robot has enabled it to detect low levels of radioactive contamination. Our preliminary tests show that RadRob15 can be easily used in nuclear medicine departments as a device for quick surveys which identifies the presence or absence of radioactive contamination.

  8. Future development of nuclear energy in the republic of Kazakhstan; Die kuenftige Entwicklung der Kernenergie in der Republik Kasachstan

    Energy Technology Data Exchange (ETDEWEB)

    Cherepnin, Y.S. [Inst. fuer Atomenergie, staatl. Zentrum fuer Kernenergie der Republik Kasachstan, Kurtschatow (Kazakhstan); Gagarinski, A.Y. [Nuclear Society International, Moscow (Russian Federation)

    1995-12-31

    Prognoses for the energy requirements for the Republic of Kazakhstan up to the year 2000 are made. The role of nuclear energy in covering the energy requirements, as well as plans for their development, are discussed. There is planned the replacement of the BN-350 reactor, the building of 2 smaller nuclear heating thermal power plants as well as the building of a nuclear power plant with 2 Russian 640 MW reactors at a later phase. 1 tab.

  9. Role of Nuclear Receptors in Central Nervous System Development and Associated Diseases

    Science.gov (United States)

    Olivares, Ana Maria; Moreno-Ramos, Oscar Andrés; Haider, Neena B.

    2015-01-01

    The nuclear hormone receptor (NHR) superfamily is composed of a wide range of receptors involved in a myriad of important biological processes, including development, growth, metabolism, and maintenance. Regulation of such wide variety of functions requires a complex system of gene regulation that includes interaction with transcription factors, chromatin-modifying complex, and the proper recognition of ligands. NHRs are able to coordinate the expression of genes in numerous pathways simultaneously. This review focuses on the role of nuclear receptors in the central nervous system and, in particular, their role in regulating the proper development and function of the brain and the eye. In addition, the review highlights the impact of mutations in NHRs on a spectrum of human diseases from autism to retinal degeneration. PMID:27168725

  10. Development of U-frame bending system for studying the vibration integrity of spent nuclear fuel

    Science.gov (United States)

    Wang, Hong; Wang, Jy-An John; Tan, Ting; Jiang, Hao; Cox, Thomas S.; Howard, Rob L.; Bevard, Bruce B.; Flanagan, Michelle

    2013-09-01

    A bending fatigue system developed to evaluate the response of spent nuclear fuel rods to vibration loads is presented. A U-frame testing setup is used for imposing bending loads on the fuel rod specimen. The U-frame setup consists of two rigid arms, side connecting plates to the rigid arms, and linkages to a universal testing machine. The test specimen's curvature is obtained through a three-point deflection measurement method. The tests using surrogate specimens with stainless steel cladding revealed increased flexural rigidity under unidirectional cyclic bending, significant effect of cladding-pellets bonding on the response of surrogate rods, and substantial cyclic softening in reverse bending mode. These phenomena may cast light on the expected response of a spent nuclear fuel rod. The developed U-frame system is thus verified and demonstrated to be ready for further pursuit in hot-cell tests.

  11. Verification of nuclear fuel plates by a developed non-destructive assay method

    Science.gov (United States)

    El-Gammal, W.; El-Nagdy, M.; Rizk, M.; Shawky, S.; Samei, M. A.

    2005-11-01

    Nuclear material (NM) verification is a main target for NM accounting and control. In this work a new relative non-destructive assay technique has been developed to verify the uranium mass content in nuclear fuel. The technique uses a planar high-resolution germanium gamma ray spectrometer in combination with the MCNP-4B Monte Carlo transport code. A standard NM sample was used to simulate the assayed NM and to determine the average intrinsic full energy peak efficiency of the detector for assayed configuration. The developed technique was found to be capable of verifying the operator declarations with an average accuracy of about 2.8% within a precision of better than 4%.

  12. Development of safety assessment of nuclear power plants using indicators; Ydinvoimalaitosten turvallisuuden arvioinnin kehittaeminen tunnuslukujen avulla

    Energy Technology Data Exchange (ETDEWEB)

    Tiippana, P.

    1997-11-01

    The study is based on an indicator system which is under development at the Radiation and Nuclear Safety Authority (STUK). The goal of this study was to define and develop both PSA-based indicators and indicators from failure statistics. As PSA-based indicators the possibility was studied to define and express the risk importance of exemptions from the Technical Specifications, failures, preventive maintenance and other disconnections of devices covered by the Technical Specifications, operating events covered by Guide YVL 1.5 and plant modifications. In this piece of research the applicability of plant specific living PSA-models used for calculation of indicators was examined. The research included both Loviisa and Olkiluoto nuclear power plants in Finland. 47 refs.

  13. Annual report on the development and characterization of solidified forms for nuclear wastes, 1979

    Energy Technology Data Exchange (ETDEWEB)

    Chick, L.A.; McVay, G.L.; Mellinger, G.B.; Roberts, F.P.

    1980-12-01

    Development and characterization of solidified nuclear waste forms is a major continuing effort at Pacific Northwest Laboratory. Contributions from seven programs directed at understanding chemical composition, process conditions, and long-term behaviors of various nuclear waste forms are included in this report. The major findings of the report are included in extended figure captions that can be read as brief technical summaries of the research, with additional information included in a traditional narrative format. Waste form development proceeded on crystalline and glass materials for high-level and transuranic (TRU) wastes. Leaching studies emphasized new areas of research aimed at more basic understanding of waste form/aqueous solution interactions. Phase behavior and thermal effects research included studies on crystal phases in defense and TRU waste glasses and on liquid-liquid phase separation in borosilicate waste glasses. Radiation damage effects in crystals and glasses from alpha decay and from transmutation are reported.

  14. Inhibition of CRM1-mediated nuclear export of influenza A nucleoprotein and nuclear export protein as a novel target for antiviral drug development.

    Science.gov (United States)

    Chutiwitoonchai, Nopporn; Mano, Takafumi; Kakisaka, Michinori; Sato, Hirotaka; Kondoh, Yasumitsu; Osada, Hiroyuki; Kotani, Osamu; Yokoyama, Masaru; Sato, Hironori; Aida, Yoko

    2017-07-01

    An anti-influenza compound, DP2392-E10 based on inhibition of the nuclear export function of the viral nucleoprotein-nuclear export signal 3 (NP-NES3) domain was successfully identified by our previous high-throughput screening system. Here, we demonstrated that DP2392-E10 exerts its antiviral effect by inhibiting replication of a broad range of influenza A subtypes. In regard to the molecular mechanism, we revealed that DP2392-E10 inhibits nuclear export of both viral NP and nuclear export protein (NEP). More specifically, in vitro pull-down assays revealed that DP2392-E10 directly binds cellular CRM1, which mediates nuclear export of NP and NEP. In silico docking suggested that DP2392-E10 binds at a region close to the HEAT9 and HEAT10 domains of CRM1. Together, these results indicate that the CRM1-mediated nuclear export function of influenza virus represents a new potential target for antiviral drug development, and also provide a core structure for a novel class of inhibitors that target this function. Copyright © 2017 Elsevier Inc. All rights reserved.

  15. Application of gas-cooled Accelerator Driven System (ADS) transmutation devices to sustainable nuclear energy development

    OpenAIRE

    2011-01-01

    The conceptual design of a pebble bed gas-cooled transmutation device is shown with the aim to evaluate its potential for its deployment in the context of the sustainable nuclear energy development, which considers high temperature reactors for their operation in cogeneration mode, producing electricity, heat and Hydrogen. As differential characteristics our device operates in subcritical mode, driven by a neutron source activated by an accelerator that adds clear safety advantages and fuel f...

  16. Future development of the research nuclear reactor IRT-2000 in Sofia

    Energy Technology Data Exchange (ETDEWEB)

    Apostolov, T.G. [Institute for Nuclear Research and Nuclear Energy, BAS, Sofia (Bulgaria)

    1999-07-01

    The present paper presents a short description of the research reactor IRT-2000 Sofia, started in 1961 and operated for 28 years. Some items are considered, connected to the improvements made in the contemporary safety requirements and the unrealized project for modernization to 5 MW. Proposals are considered for reconstruction of reactor site to a 'reactor of low power' for education purposes and as a basis for the country's nuclear technology development. (author)

  17. Privileged Communication Embryonic Development Following Somatic Cell Nuclear Transfer Impeded by Persisting Histone Methylation

    OpenAIRE

    Matoba, Shogo; Liu, Yuting; Lu, Falong; Iwabuchi, Kumiko A.; Shen, Li; Inoue, Azusa; Zhang, Yi

    2014-01-01

    Mammalian oocytes can reprogram somatic cells into a totipotent state enabling animal cloning through somatic cell nuclear transfer (SCNT). However, the majority of SCNT embryos fail to develop to term due to undefined reprogramming defects. Here we identify histone H3 lysine 9 trimethylation (H3K9me3) of donor cell genome as a major epigenetic barrier for efficient reprogramming by SCNT. Comparative transcriptome analysis identified reprogramming resistant regions (RRRs) that are expressed n...

  18. Developments in the JRodos decision support system for off-site nuclear emergency management and rehabilitation

    Energy Technology Data Exchange (ETDEWEB)

    Landman, Claudia [Karlsruher Institut fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany); Pro-Science GmbH, Ettlingen (Germany); Raskob, Wolfgang; Trybushnyi, Dmytro [Karlsruher Institut fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany)

    2016-07-01

    JRodos is a non-commercial computer-based decision support system for nuclear accidents. The simulation models for assessing radiological and other consequences and the system features and components allow real-time operation for off-site emergency management as well as the use as a tool for preparing exercises and pre-plannng of countermeasures. There is an active user community that takes influence on further developments.

  19. Development of fast neutron pinhole camera using nuclear emulsion for neutron emission profile measurement in KSTAR

    Science.gov (United States)

    Izumi, Y.; Tomita, H.; Nakayama, Y.; Hayashi, S.; Morishima, K.; Isobe, M.; Cheon, M. S.; Ogawa, K.; Nishitani, T.; Naka, T.; Nakano, T.; Nakamura, M.; Iguchi, T.

    2016-11-01

    We have developed a compact fast neutron camera based on a stack of nuclear emulsion plates and a pinhole collimator. The camera was installed at J-port of Korea superconducting tokamak advanced research at National Fusion Research Institute, Republic of Korea. Fast neutron images agreed better with calculated ones based on Monte Carlo neutron simulation using the uniform distribution of Deuterium-Deuterium (DD) neutron source in a torus of 40 cm radius.

  20. The Construction of Goshute Political Identity: Negotiation of Voice Regarding Nuclear Waste Policy Development

    OpenAIRE

    Clarke, Tracylee

    2017-01-01

    This article examines the relationship between political identity and voice through an analysis of conflict between members of the same Native American nation over the development of environmental policy. Grounding this study in the work of Paul Ricoeur and his theory of narrated identity and using Senecah’s “Trinity of Voice” as an organizing analytical framework, I examine communication and negotiation of voice among members of the Skull Valley Goshute tribe regarding the storing of nuclear...

  1. Development of improved thermal hydraulics and fuel performance technology; development of turbulence model for flow analysis in nuclear fuel assembly

    Energy Technology Data Exchange (ETDEWEB)

    Joo, W. K.; Kong, D. W.; Park, H. Z. [Yonsei University, Seoul (Korea)

    2001-04-01

    The flow through a nuclear rod bundle with mixing vanes are very complex and required a suitable turbulence model to be predicted accurately. Subchannel flow in a nuclear bundle having vanes to mix flow appears complex turbulent flow. Objective of this study is to develop turbulence model which can predict complex flow. Also, the module will be produced, which can implement the developed turbulence model in the CFX code. The selected turbulence models are k-epsilon model, non-linear k-epsilon model, Reynolds stress model and modified Reynolds stress model to test their performance in the prediction of the flow in nuclear assembly. These models are tested for a 2-D backwise step flow, square duct flow, rod bundle flow and subchannel flow using CFX. The modules, which can implement Reynolds stress model and non-linear k-epsilon odel in CFX code, are produced. The advantages and disadvantages for these turbulence models are described and the limitation of implementation of non-linear model in CFX code is discussed. The results obtained from the research would give a help for the development of turbulence model which can accurately predict the flow through the rod bundles with mixing vanes. 18 refs., 37 figs., 8 tabs. (Author)

  2. Development of renal simulators for use in nuclear medicine; Desenvolvimento de simuladores renais para uso em medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Dullius, Marcos Alexandre

    2014-09-01

    Quality control programs in nuclear medicine include verifying the efficiency of all equipment used for diagnosis and therapy, including scintillation cameras. To that end, we have developed and evaluated the performance of four phantom kidneys - two static anthropomorphic, one semi-dynamic, and one dynamic - to acquire static and dynamic renal scintigraphic images. The static anthropomorphic phantoms were used to characterize and evaluate the response of the processing system for different concentrations of radionuclides through static renal scintigraphy images ({sup 99m}Tc-DMSA), obtained with posterior, right posterior oblique, left posterior oblique, and anterior incidences. The static phantoms were made in two ways; one was made of acrylic from a mold of a pair of human kidneys preserved in formalin, and the second was built with acrylonitrile butadiene styrene (ABS), in a 3D printer using the Slicer program, based on a computed tomography (CT) of the thorax, using the Slicer program. The semi-dynamic and dynamic phantoms were constructed to characterize and evaluate images of dynamic renal scintigraphy. In the semi-dynamic phantom, the injection of radiotracer was performed manually, whereas in the dynamic phantom, the radiotracer was automatically injected through an injector system. With the semi-dynamic phantom, it was possible to analyze the formation of a renogram with normal renal scintigraphic appearance using an imaging system. The simulations obtained from the dynamic phantom simulator enabled studies of normal renal scintigraphy and four other forms of renograms. The static anthropomorphic phantom kidneys proved to be efficient for use in evaluations of varying concentrations of radionuclides. The dynamic phantom kidney was useful for analysis of scintigraphic images and obtaining different pathways for elimination of the radioisotope, allowing for analysis of different renograms. Therefore, the new kidney phantoms would be useful for quality

  3. Development of Asset Fault Signatures for Prognostic and Health Management in the Nuclear Industry

    Energy Technology Data Exchange (ETDEWEB)

    Vivek Agarwal; Nancy J. Lybeck; Randall Bickford; Richard Rusaw

    2014-06-01

    Proactive online monitoring in the nuclear industry is being explored using the Electric Power Research Institute’s Fleet-Wide Prognostic and Health Management (FW-PHM) Suite software. The FW-PHM Suite is a set of web-based diagnostic and prognostic tools and databases that serves as an integrated health monitoring architecture. The FW-PHM Suite has four main modules: Diagnostic Advisor, Asset Fault Signature (AFS) Database, Remaining Useful Life Advisor, and Remaining Useful Life Database. This paper focuses on development of asset fault signatures to assess the health status of generator step-up generators and emergency diesel generators in nuclear power plants. Asset fault signatures describe the distinctive features based on technical examinations that can be used to detect a specific fault type. At the most basic level, fault signatures are comprised of an asset type, a fault type, and a set of one or more fault features (symptoms) that are indicative of the specified fault. The AFS Database is populated with asset fault signatures via a content development exercise that is based on the results of intensive technical research and on the knowledge and experience of technical experts. The developed fault signatures capture this knowledge and implement it in a standardized approach, thereby streamlining the diagnostic and prognostic process. This will support the automation of proactive online monitoring techniques in nuclear power plants to diagnose incipient faults, perform proactive maintenance, and estimate the remaining useful life of assets.

  4. Building up the nucleus: nuclear organization in the establishment of totipotency and pluripotency during mammalian development

    Science.gov (United States)

    Borsos, Máté; Torres-Padilla, Maria-Elena

    2016-01-01

    In mammals, epigenetic reprogramming, the acquisition and loss of totipotency, and the first cell fate decision all occur within a 3-d window after fertilization from the one-cell zygote to the formation of the blastocyst. These processes are poorly understood in molecular detail, yet this is an essential prerequisite to uncover principles of stem cells, chromatin biology, and thus regenerative medicine. A unique feature of preimplantation development is the drastic genome-wide changes occurring to nuclear architecture. From studying somatic and in vitro cultured embryonic stem cells (ESCs) it is becoming increasingly established that the three-dimensional (3D) positions of genomic loci relative to each other and to specific compartments of the nucleus can act on the regulation of gene expression, potentially driving cell fate. However, the functionality, mechanisms, and molecular characteristics of the changes in nuclear organization during preimplantation development are only now beginning to be unraveled. Here, we discuss the peculiarities of nuclear compartments and chromatin organization during mammalian preimplantation development in the context of the transition from totipotency to pluripotency. PMID:26980186

  5. Phase II: Field Detector Development For Undeclared/Declared Nuclear Testing For Treaty Verfiation Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Kriz, M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hunter, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Riley, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-10-02

    Radioactive xenon isotopes are a critical part of the Comprehensive Nuclear Test Ban Treaty (CTBT) for the detection or confirmation of nuclear weapons tests as well as on-site treaty verification monitoring. On-site monitoring is not currently conducted because there are no commercially available small/robust field detector devices to measure the radioactive xenon isotopes. Xenon is an ideal signature to detect clandestine nuclear events since they are difficult to contain and can diffuse and migrate through soils due to their inert nature. There are four key radioxenon isotopes used in monitoring: 135Xe (9 hour half-life), 133mXe (2 day half-life), 133Xe (5 day half-life) and 131mXe (12 day half-life) that decay through beta emission and gamma emission. Savannah River National Laboratory (SRNL) is a leader in the field of gas collections and has developed highly selective molecular sieves that allow for the collection of xenon gas directly from air. Phase I assessed the development of a small, robust beta-gamma coincidence counting system, that combines collection and in situ detection methodologies. Phase II of the project began development of the custom electronics enabling 2D beta-gamma coincidence analysis in a field portable system. This will be a significant advancement for field detection/quantification of short-lived xenon isotopes that would not survive transport time for laboratory analysis.

  6. The Necessity of Developing Nuclear Energy in Romania in the Context of Global Economy Expansion

    Directory of Open Access Journals (Sweden)

    Dana-Elena MARCEAN HOLBAN

    2015-12-01

    Full Text Available Energy is one of the most important elements of the global economy, being the basic unit of world economic development. In the energy mix, nuclear energy - more than any other type of energy - has generated and will always generate a series of controversies. This article aims to emphasize the economic and social implications, further than the general purpose of developing nuclear energy: national energetic security. With the starting point clearly defined – the history already written by the operation of Unit 1 and 2 – the path to discover all its elements seems to be clear, although a whole range of unknown issues can rise many different interpretations. In Romania, nuclear energy produces 18% of Romania's electricity supplies. Development of Units 3 and 4 of the Cernavoda site could more than double this capacity. This will have major implications in the trading market, significantly influencing the price of electricity not only nationally, but, in the context coupling energy markets, as well as at regional level. It is also risen the question of using this additional production. Depending on the time of commissioning, this quantity of energy that now seems overmuch, can be used for export, to reduce the use of fossil fuels and to continue to obtain electricity in the context of a system based on power plants that use fossil fuels, whose lifespan is nearing completion.

  7. Nuclear structure

    CERN Document Server

    Nazarewicz, W

    1999-01-01

    Current developments in nuclear structure are discussed from a theoretical perspective. The studies of the nuclear many-body system provide us with invaluable information about the nature of the nuclear interaction, nucleonic correlations at various energy-distance scales, and the modes of the nucleonic matter.

  8. The development of radiation hardened robot for nuclear facility - Development of embedded controller for hydraulic robot

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Byung Kook; Kim, Jae Kwon [Korea Advanced Institute of Science and Technology, Taejon (Korea)

    2000-04-01

    We designed and implemented a reliable hierarchical control system for hydraulic robots for nuclear power plant maintenance. In hazardous environments such as nuclear power plants, robot systems or automated equipment should be used instead of human being for maintenance and repair. Such robot should guarantee high reliability in hazardous environments such as high radiation or high temperature. The overall system is composed of three hierarchical subsystems: i) supervisory controller in safe zone for operator interaction with monitoring and commanding and graphic user interface, ii) master controller in semi-hazardous zone for control function, and iii) slave controller in hazardous zone for sensing and actuation. These subsystems are connected with suitable communication channels: a) master-slave communication channel implemented with CAN (Control Area Network) and b) supervisory-master communication with Ethernet. The master and the slave controllers construct a feedback closed-loop control system. In order to improve reliability, the slave controller is duplicated using cold-standby scheme, and master-slave communication channel is also duplicated. The overall system is implemented harmonically, and we obtained fast control interval of 1msec, which is sufficient for high-performance real-time control. 12 refs., 58 figs., 13 tabs. (Author)

  9. FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume I

    Energy Technology Data Exchange (ETDEWEB)

    Abdou, M.

    1984-10-01

    The following chapters are included in this study: (1) fusion nuclear issues, (2) survey of experimental needs, (3) requirements of the experiments, (4) non-fusion facilities, (5) fusion facilities for nuclear experiments, and (6) fusion research and development scenarios. (MOW)

  10. Mitigating Community Impacts of Energy Development: Some Examples for Coal and Nuclear Generating Plants in the United States.

    Science.gov (United States)

    Peelle, Elizabeth

    The Hartsville, Tennessee nuclear reactor site, the coal plant at Wheatland, Wyoming, and the nuclear plant at Skagit, Washington have mitigation plans developed in response to a federal, state, and local regulatory agency, respectively; the three mitigation plans aim at internalizing community-level social costs and benefits during the…

  11. Examination of various roles for covariance matrices in the development, evaluation, and application of nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Smith, D.L.

    1988-01-01

    The last decade has been a period of rapid development in the implementation of covariance-matrix methodology in nuclear data research. This paper offers some perspective on the progress which has been made, on some of the unresolved problems, and on the potential yet to be realized. These discussions address a variety of issues related to the development of nuclear data. Topics examined are: the importance of designing and conducting experiments so that error information is conveniently generated; the procedures for identifying error sources and quantifying their magnitudes and correlations; the combination of errors; the importance of consistent and well-characterized measurement standards; the role of covariances in data parameterization (fitting); the estimation of covariances for values calculated from mathematical models; the identification of abnormalities in covariance matrices and the analysis of their consequences; the problems encountered in representing covariance information in evaluated files; the role of covariances in the weighting of diverse data sets; the comparison of various evaluations; the influence of primary-data covariance in the analysis of covariances for derived quantities (sensitivity); and the role of covariances in the merging of the diverse nuclear data information. 226 refs., 2 tabs.

  12. SRNL CRP progress report [Development of Melt Processed Ceramics for Nuclear Waste Immobilization

    Energy Technology Data Exchange (ETDEWEB)

    Amoroso, J. [Savannah River National Laboratory, Aiken, SC (United States); Marra, J. [Savannah River National Laboratory, Aiken, SC (United States)

    2014-10-02

    A multi-phase ceramic waste form is being developed at the Savannah River National Laboratory (SRNL) for treatment of secondary waste streams generated by reprocessing commercial spent nuclear. The envisioned waste stream contains a mixture of transition, alkali, alkaline earth, and lanthanide metals. Ceramic waste forms are tailored (engineered) to incorporate waste components as part of their crystal structure based on knowledge from naturally found minerals containing radioactive and non-radioactive species similar to the radionuclides of concern in wastes from fuel reprocessing. The ability to tailor ceramics to mimic naturally occurring crystals substantiates the long term stability of such crystals (ceramics) over geologic timescales of interest for nuclear waste immobilization [1]. A durable multiphase ceramic waste form tailored to incorporate all the waste components has the potential to broaden the available disposal options and thus minimize the storage and disposal costs associated with aqueous reprocessing.

  13. Fabrication and closure development of nuclear waste containers for storage at the Yucca Mountain, Nevada repository

    Energy Technology Data Exchange (ETDEWEB)

    Russell, E.W.; Nelson, T.A. [Lawrence Livermore National Lab., CA (USA); Domian, H.A.; LaCount, D.F.; Robitz, E.S.; Stein, K.O. [Babcock and Wilcox Co., New Orleans, LA (USA)

    1989-04-01

    US Congress and the President have determined that the Yucca Mountain site in Nevada is to be characterized to determine its suitability for construction of the first US high-level nuclear waste repository. Work in connection with this site is carried out within the Yucca Mountain Project (YMP). Lawrence Livermore National Laboratory (LLNL) has the responsibility for designing, developing, and projecting the performance of the waste package for the permanent storage of high-level nuclear waste. Babcock & Wilcox (B & W) is involved with the YMP as a subcontractor to LLNL. B & W`s role is to recommend and demonstrate a method for fabricating the metallic waste container and a method for performing the final closure of the container after it has been filled with waste. Various fabrication and closure methods are under consideration for the production of containers. This paper presents progress to date in identifying and evaluating the candidate manufacturing processes. 2 refs., 1 fig., 7 tabs.

  14. Recent developments in chiral dynamics of hadrons and hadrons in a nuclear medium

    CERN Document Server

    Oset, E; Vacas, M J V; Kaskulov, M; Roca, L; Magas, V K; Ramos, A; Toki, H

    2007-01-01

    In this talk I present recent developments in chiral dynamics of hadrons and hadrons in a medium addressing the following points: interaction of the octet of pseudoscalar mesons with the octet of baryons of the nucleon, showing recent experimental evidence on the existence of two $\\Lambda(1405)$ states, the interaction of the octet of pseudoscalar mesons with the decuplet of baryons of the $\\Delta$, with particular emphasis on the $\\Lambda(1520)$ resonance, dynamically generated by this interaction. Then I review the interaction of kaons in a nuclear medium and briefly discuss the situation around the claims of deeply bound states in nuclei. The large renormalization of the $\\Lambda(1520)$ in the nuclear medium is shown as another example of successful application of the chiral unitary techniques.

  15. Standard Reference Development of nuclear material for Tensile and Hardness Test Properties

    Energy Technology Data Exchange (ETDEWEB)

    Choo, Y. S.; Kim, D. S.; Yoo, B. O.; Ahn, S. B.; Baik, S. J.; Chun, Y. B.; Kim, K. H.; Hong, K. P.; Ryu, W. S

    2007-12-15

    Standard reference is a official approved data such a coefficient of physics, approved material properties, and etc., which should be analyzed and evaluated by scientific method to acquire official approval for accuracy and credibility of measured data and information. So it could be used broadly and continuously by various fields of nation and society. It is classified to effective standard reference, verified standard reference, and certified standard reference. There are sixteen fields in designated standard references such a physical chemistry field, material field, metal field, and the others. The standard reference of neutron irradiated nuclear structural material is classified to metal field. This report summarized the whole processes about data collection, data production, data evaluation and the suggestion of details evaluation technical standard for tensile and hardness properties, which were achieved by carry out the project 'nuclear material standard reference development' as a result.

  16. In-laboratory development of an automatic track counting system for solid state nuclear track detectors

    Science.gov (United States)

    Uzun, Sefa Kemal; Demiröz, Işık; Ulus, İzzet

    2017-01-01

    In this study, an automatic track counting system was developed for solid state nuclear track detectors (SSNTD). Firstly the specifications of required hardware components were determined, and accordingly the CCD camera, microscope and stage motor table was supplied and integrated. The system was completed by developing parametric software with VB.Net language. Finally a set of test intended for radon activity concentration measurement was applied. According to the test results, the system was enabled for routine radon measurement. Whether the parameters of system are adjusted for another SSNTD application, it could be used for other fields of SSNTD like neutron dosimetry or heavy charged particle detection.

  17. Development of nuclear thermal hydraulic verification tests and evaluation technology - Development of the ultrasonic method for two-phase mixture level measurement in nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    No, Hee Cheon; Kim, Sang Jae; Kim, Hyung Tae; Moon, Young Min [Korea Advanced Institute of Science and Technology, Taejon (Korea)

    2000-04-01

    An ultrasonic method is developed for the measurement of the two-phase mixture level in the reactor vessel or steam generator. The ultrasonic method is selected among the several non-nuclear two-phase mixture level measurement methods through two steps of selection procedure. A commercial ultrasonic level measurement method is modified for application into the high temperature, pressure, and other conditions. The calculation method of the ultrasonic velocity is modified to consider the medium as the homogeneous mixture of air and steam, and to be applied into the high temperature and pressure conditions. The cross-correlation technique is adopted as a detection method to reduced the effects of the attenuation and the diffused reflection caused by surface fluctuation. The waveguides are developed to reduce the loss of echo and to remove the effects of obstructs. The present experimental study shows that the developed ultrasonic method measures the two-phase mixture level more accurately than the conventional methods do. 21 refs., 60 figs., 13 tabs. (Author)

  18. Development of a dynamical systems model of plant programmatic performance on nuclear power plant safety risk

    Energy Technology Data Exchange (ETDEWEB)

    Hess, Stephen M. [Sensortex, Inc., 515 Schoolhouse Road, Kennett Square, PA 19348 (United States)]. E-mail: smhess@sensortex.com; Albano, Alfonso M. [Department of Physics, Bryn Mawr College, Bryn Mawr, PA 19010 (United States); Gaertner, John P. [Electric Power Research Institute, 1300 Harris Boulevard, Charlotte, NC 28262 (United States)

    2005-10-01

    Application of probabilistic risk assessment (PRA) techniques to model nuclear power plant accident sequences has provided a significant contribution to understanding the potential initiating events, equipment failures and operator errors that can lead to core damage accidents. Application of the lessons learned from these analyses has resulted in significant improvements in plant operation and safety. However, this approach has not been nearly as successful in addressing the impact of plant processes and management effectiveness on the risks of plant operation. The research described in this paper presents an alternative approach to addressing this issue. In this paper we propose a dynamical systems model that describes the interaction of important plant processes on nuclear safety risk. We discuss development of the mathematical model including the identification and interpretation of significant inter-process interactions. Next, we review the techniques applicable to analysis of nonlinear dynamical systems that are utilized in the characterization of the model. This is followed by a preliminary analysis of the model that demonstrates that its dynamical evolution displays features that have been observed at commercially operating plants. From this analysis, several significant insights are presented with respect to the effective control of nuclear safety risk. As an important example, analysis of the model dynamics indicates that significant benefits in effectively managing risk are obtained by integrating the plant operation and work management processes such that decisions are made utilizing a multidisciplinary and collaborative approach. We note that although the model was developed specifically to be applicable to nuclear power plants, many of the insights and conclusions obtained are likely applicable to other process industries.

  19. Development of automatic reactor vessel inspection systems: development of data acquisition and analysis system for the nuclear vessel weld

    Energy Technology Data Exchange (ETDEWEB)

    Park, C. H.; Lim, H. T.; Um, B. G. [Korea Advanced Institute of Science and Technology, Taejeon (Korea)

    2001-03-01

    The objective of this project is to develop an automated ultrasonic data acquisition and data analysis system to examine the reactor vessel weldsIn order to examine nuclear vessel welds including reactor pressure vessel(RPV), huge amount of ultrasonic data from 6 channels should be able to be on-line processed. In addition, ultrasonic transducer scanning device should be remotely controlled, because working place is high radiation area. This kind of an automated ultrasonic testing equipment has not been developed domestically yet In order to develop an automated ultrasonic testing system, RPV ultrasonic testing equipments developed in foreign countries were investigated and the capability of high speed ultrasonic signal processing hardwares was analyzed in this study, ultrasonic signal processing system was designed. And also, ultrasonic data acquisition and analysis software was developed. 11 refs., 6 figs., 9 tabs. (Author)

  20. Development of Nuclear R and D Man-power Genealogy DB and preparation of Guiding Principle in Assets Application for Nuclear R and D Fund

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dong Uk; Song, Seung Hyun; Kim, Hak Jun; Chung, Chul Eun

    2007-08-15

    Information search for nuclear professional man-power, technology genealogy search, project participation history etc. is serviced, and present limits to KAERI additionally, but constructed Site-Based DB that service is embodied as well as subject responsible person's pedigree. Information of professional man-power include origin school, last degree, distinction of sex, age etc. and technology genealogy consist of NuTRM classification, national science technology classification, and technology tree system classified in KAERI. Technology possession present condition for professional man-power of only KAERI is included within DB. Hereafter, professional manpower of the other nuclear energy company should be strengthened on the basis of DB structure that is developed. Technology tree system classified in KAERI also required to be strengthened on the man-power DB that has effectiveness for long-term as that embody by technology tree system which can represent nuclear energy through the verification of the other nuclear energy company. By applying readying guiding principle in assets application for nuclear R and D fund, secure lucency of assets application.

  1. Effects of growth hormone on nuclear maturation of ovine oocytes and subsequent embryo development.

    Science.gov (United States)

    Shirazi, A; Shams-Esfandabadi, N; Ahmadi, E; Heidari, B

    2010-06-01

    The objective of this study was to determine the effect of the presence of recombinant ovine growth hormone either alone or together with follicle stimulating hormone (FSH) during ovine oocyte in vitro maturation (IVM) on nuclear maturation and subsequent embryo development. Moreover, the effect of growth hormine (GH) on embryo development whether influenced by the presence of foetal bovine serum (FBS) was assessed. The abattoir-derived oocytes were randomly divided into four treatment groups and cultured in maturation medium supplemented with: (i) 0.05 IU/ml FSH; (ii) 300 ng/ml roGH; (iii) FSH + roGH; and (iv) no FSH and GH (control). The percentages of germinal vesicle-stage oocytes in GH-treated group after 8 h of culture was significantly higher than the FSH and FSH + GH groups and lower than control (22.4%, 8.7%, 9.1%, and 32% respectively). The percentage of MII-stage oocytes was significantly increased in the presence of GH after 16 and 24 h of culture compared to the control (44.7% and 83.1% vs 32.6% and 73.6% respectively). There was no significant synergism between GH and FSH in terms of nuclear maturation. The blastocyst rates in serum-supplemented groups were enhanced by the presence of FSH and GH compared to the control (35.4% and 31.3 vs 11.4% respectively). Compared with either GH or FSH alone, the subsequent embryo development (blastocyst rate), however, was negatively influenced by co-presence of both hormones (22.8%). In contrast, the corresponding values were not affected in the absence of serum. In conclusion, GH had positive effect on nuclear maturation of sheep oocytes. Moreover, the pattern of the effect of GH on embryo development was influenced by the presence of FBS during IVM.

  2. Development of a seismic damage assessment program for nuclear power plant structures

    Energy Technology Data Exchange (ETDEWEB)

    Koh, Hyun Moo; Cho, Yang Heui; Shin, Hyun Mok [Seoul National Univ., Seoul (Korea, Republic of)] (and others)

    2001-12-15

    The most part of the nuclear power plants operating currently in Korea are more than 20 years old and obviously we cannot pretend that their original performance is actually maintained. In addition, earthquake occurrences show an increasing trend all over the world, and Korea can no more be considered as a zone safe from earthquake. Therefore, need is to guarantee the safety of these power plant structures against seismic accident, to decide to maintain them operational and to obtain data relative to maintenance/repair. Such objectives can be reached by damage assessment using inelastic seismic analysis considering aging degradation. It appears to be more important particularly for the structure enclosing the nuclear reactor that must absolutely protect against any radioactive leakage. Actually, the tendency of the technical world, led by the OECD/NEA, BNL in the United States, CEA in France and IAEA, is to develop researches or programs to assess the seismic safety considering aging degradation of operating nuclear power plants. Regard to the above-mentioned international technical trend, a technology to establish inelastic seismic analysis considering aging degradation so as to assess damage level and seismic safety margin appears to be necessary. Damage assessment and prediction system to grasp in real-time the actual seismic resistance capacity and damage level by 3-dimensional graphic representations are also required.

  3. Development of a seismic damage assessment program for nuclear power plant structures

    Energy Technology Data Exchange (ETDEWEB)

    Koh, Hyun Moo; Cho, Ho Hyun; Cho, Yang Hui [Seoul National Univ., Seoul (Korea, Republic of)] (and others)

    2000-12-15

    Some of nuclear power plants operating currently in Korea have been passed about 20 years after construction. Moreover, in the case of KORI I the service year is over 20 years, so their abilities are different from initial abilities. Also, earthquake outbreak increase, our country is not safe area for earthquake. Therefore, need is to guarantee the safety of these power plant structures against seismic accident, to decide to maintain them operational and to obtain data relative to maintenance/repair. Such objectives can be reached by damage assessment using inelastic seismic analysis considering aging degradation. It appears to be more important particularly for the structure enclosing the nuclear reactor that must absolutely protect against any radioactive leakage. Actually, the tendency of the technical world, led by the OECD/NEA, BNL in the United States, CEA in France and IAEA, is to develop researches or programs to assess the seismic safety considering aging degradation of operating nuclear power plants. Regard to the above-mentioned international technical trend, a technology to establish inelastic seismic analysis considering aging degradation so as to assess damage level and seismic safety margin appears to be necessary. Damage assessment and prediction system to grasp in real-time the actual seismic resistance capacity and damage level by 3-dimensional graphic representations are also required.

  4. Development of innovative technological base for large-scale nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Adamov, E.O.; Dedul, A.V.; Orlov, V.V.; Rachkov, V.I.; Slesarev, I.S. [ITC ' ' PRORYV' ' Project, Moscow (Russian Federation)

    2017-04-15

    The problems of the Nuclear Power (NP) further development as well as the ways of their resolution on the basis of innovative fast reactor concepts and the Closed Equilibrium Fuel Cycle (CEFC) are analyzed. The new paradigm of NP and the corresponding NP super task are declared. The corresponding super task could be considered a transition to the vital risk free nuclear power through the guaranteed elimination/suppression of all their vital risks and threats (or their transformation to the category of some ordinary risks and threats) on the base of ''natural safety principle''. The project of Rosatom State Corporation (named ''PRORYV'') is launched within the Federal Target Program ''Nuclear power technologies of new generation for 2010 to 2015 and in perspective till 2020''. It has been planned just for these goals achievement. Super-task solution is quite ''on teeth'' to PRORYV project which is initially focused on the ''natural safety'' realization. This project is aimed, in particular, at construction of the demonstration lead cooled reactor BREST-300-OD and the enterprise for equilibrium fuel cycle closing.

  5. Developing a structural health monitoring system for nuclear dry cask storage canister

    Science.gov (United States)

    Sun, Xiaoyi; Lin, Bin; Bao, Jingjing; Giurgiutiu, Victor; Knight, Travis; Lam, Poh-Sang; Yu, Lingyu

    2015-03-01

    Interim storage of spent nuclear fuel from reactor sites has gained additional importance and urgency for resolving waste-management-related technical issues. In total, there are over 1482 dry cask storage system (DCSS) in use at US plants, storing 57,807 fuel assemblies. Nondestructive material condition monitoring is in urgent need and must be integrated into the fuel cycle to quantify the "state of health", and more importantly, to guarantee the safe operation of radioactive waste storage systems (RWSS) during their extended usage period. A state-of-the-art nuclear structural health monitoring (N-SHM) system based on in-situ sensing technologies that monitor material degradation and aging for nuclear spent fuel DCSS and similar structures is being developed. The N-SHM technology uses permanently installed low-profile piezoelectric wafer sensors to perform long-term health monitoring by strategically using a combined impedance (EMIS), acoustic emission (AE), and guided ultrasonic wave (GUW) approach, called "multimode sensing", which is conducted by the same network of installed sensors activated in a variety of ways. The system will detect AE events resulting from crack (case for study in this project) and evaluate the damage evolution; when significant AE is detected, the sensor network will switch to the GUW mode to perform damage localization, and quantification as well as probe "hot spots" that are prone to damage for material degradation evaluation using EMIS approach. The N-SHM is expected to eventually provide a systematic methodology for assessing and monitoring nuclear waste storage systems without incurring human radiation exposure.

  6. A future for nuclear sites beyond their service life. Nuclear site value development; Un avenir pour les sites nucleaires en fin de cycle. Valorisation des sites nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    As the nuclear industry moves into a new development phase, many facilities built in the fifties and sixties are reaching the end of their service life. Dismantling them and rehabilitating the sites on which they stand is a major industrial challenge which will give rise to a number of new projects. AREVA has more than 20 years' experience in these highly technical fields. As more and more sites reach the end of their service life, AREVA considers nuclear site value development as a fully-fledged industrial activity. The group's competencies in this field have been grouped together to form a dedicated entity: the Nuclear Site Value Development Business Unit, created in 2008. Several billion euros are invested in site value development projects which are far-reaching and complex, and often last for several decades. Long before work actually begins, lengthy studies and preparations are required to schedule operations, select the techniques to be used and optimize costs and deadlines. The Nuclear Site Value Development BU is currently working on four major projects involving its own facilities and those of the CEA: - La Hague: dismantling of the first generation of used fuel recycling facilities. Between 1966 and 1998, almost 5,000 tons of used fuel from graphite-moderated gas-cooled reactors, 4,500 tons of light water reactor fuel, as well as fuel from fast reactors and research reactors, were treated at UP2 400, the very first industrial recycling plant on the La Hague site. - Marcoule: first-time dismantling of a recycling plant. 1,000 rooms to be cleaned up, 30,000 tons of waste to be treated, 30 years of work. - Cadarache: first-time dismantling of a Mox fuel fabrication plant. The Cadarache plant was commissioned in 1962 to fabricate fuel for fast reactors; this was followed by MOX fuel for light water reactors, an activity which continued until the plant was shut down in 2003. - Annecy and Veurey: giving a new lease of life to former industrial sites

  7. Next Generation Nuclear Plant Reactor Pressure Vessel Materials Research and Development Plan (PLN-2803)

    Energy Technology Data Exchange (ETDEWEB)

    J. K. Wright; R. N. Wright

    2010-07-01

    The U.S. Department of Energy (DOE) has selected the High-Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production, with an outlet gas temperature in the range of 750°C, and a design service life of 60 years. The reactor design will be a graphite-moderated, helium-cooled, prismatic, or pebble bed reactor and use low-enriched uranium, Tri-Isotopic (TRISO)-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. This technology development plan details the additional research and development (R&D) required to design and license the NGNP RPV, assuming that A 508/A 533 is the material of construction. The majority of additional information that is required is related to long-term aging behavior at NGNP vessel temperatures, which are somewhat above those commonly encountered in the existing database from LWR experience. Additional data are also required for the anticipated NGNP environment. An assessment of required R&D for a Grade 91 vessel has been retained from the first revision of the R&D plan in Appendix B in somewhat less detail. Considerably more development is required for this steel compared to A 508/A 533 including additional irradiation testing for expected NGNP operating temperatures, high-temperature mechanical properties, and extensive studies of long-term microstructural stability.

  8. Risk and social construction of nuclear power development in China: local people’s participation in civil nuclear issues in China at the start of the 21st century

    OpenAIRE

    Fang, Xiang

    2011-01-01

    China’s civil nuclear power programme is a sensitive topic which has seldom been researched by social or political scientists inside or outside of China. In the past, public participation activities in relation to nuclear power issues in China were rare. However, in 2005, when the central government decided to promote civil nuclear development and build 40 more nuclear reactors within the next 20 years, the public started to become aware of the potential environmental risks tha...

  9. Development of a Flexible Computerized Management Infrastructure for a Commercial Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Ali, Syed Firasat; Hajek, Brian K.; Usman, Shoaib

    2006-05-01

    The report emphasizes smooth transition from paper-based procedure systems (PBPSs) to computer-based procedure systems (CBPSs) for the existing commercial nuclear power plants in the U.S. The expected advantages and of the transition are mentioned including continued, safe and efficient operation of the plants under their recently acquired or desired extended licenses. The report proposes a three-stage survey to aid in developing a national strategic plan for the transition from PBPSs to CBPSs. It also includes a comprehensive questionnaire that can be readily used for the first stage of the suggested survey.

  10. Development of a car-mounted nuclear material monitoring system: A prototype system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kwang Hyun [College of Dentistry, Chosun University, 375, Seosuk-Dong, Dong-Gu, Gwangju (Korea, Republic of)], E-mail: radkim@chosun.ac.kr; Jun, Jeo Young; Jun, In Sub [RadTek, Research Center and Co., Ltd., Dukjin-Dong, Yusung-Gu, Daejeon (Korea, Republic of); Kwak, Sung-Woo [Korea Institute of Nuclear Nonproliferation and Control, 573 Expo-ro, Yuseong-gu, Daejeon 305-348 (Korea, Republic of)

    2009-08-01

    We have developed a car-mounted neutron and gamma monitoring system as a nuclear material detection system (NMDS). The system has been equipped with Geiger Muller detector (GM) and NaI(Tl) detectors for gamma-ray surveillance, and {sup 3}He detector for neutron surveillance. The customized interface board based on ARM core CPU and graphical user interface (GUI)-based software provide the system with counting and spectroscopy functions of gamma-ray and neutron in each window. The system showed good performances in detecting and analyzing suspicious radioactive materials even at low-level activities.

  11. Gas core nuclear thermal rocket engine research and development in the former USSR

    Energy Technology Data Exchange (ETDEWEB)

    Koehlinger, M.W.; Bennett, R.G.; Motloch, C.G. [eds.; Gurfink, M.M.

    1992-09-01

    Beginning in 1957 and continuing into the mid 1970s, the USSR conducted an extensive investigation into the use of both solid and gas core nuclear thermal rocket engines for space missions. During this time the scientific and engineering. problems associated with the development of a solid core engine were resolved. At the same time research was undertaken on a gas core engine, and some of the basic engineering problems associated with the concept were investigated. At the conclusion of the program, the basic principles of the solid core concept were established. However, a prototype solid core engine was not built because no established mission required such an engine. For the gas core concept, some of the basic physical processes involved were studied both theoretically and experimentally. However, no simple method of conducting proof-of-principle tests in a neutron flux was devised. This report focuses primarily on the development of the. gas core concept in the former USSR. A variety of gas core engine system parameters and designs are presented, along with a summary discussion of the basic physical principles and limitations involved in their design. The parallel development of the solid core concept is briefly described to provide an overall perspective of the magnitude of the nuclear thermal propulsion program and a technical comparison with the gas core concept.

  12. Prospect of Nuclear Power Today as Part of Ghana Energy Mix and Socio-Economic Development

    Directory of Open Access Journals (Sweden)

    Sylvester Attakorah Birikorang

    2012-06-01

    Full Text Available Energy is essential for economic development and improvement of quality of life in every human settlement. Considering her economic aspirations and population growth, Ghana’s energy demand, particularly that of electricity is sure to rise in coming years. Ghana’s total installed electricity generation capacity currently stands at 1810MW, with a current population is estimated to be 24.4 million based on 2010 population census. The country and for that matter is confronted with the challenge of meeting her energy needs in a cost effective and environmentally friendly manner so as to attain middle income status. This policy document presents nuclear power as the most versatile, convenient and competitive source of electrical energy that should be planned for now and will be worth introducing into Ghana’s energy mix for sustainable development of the country.  Nuclear Power Plants can serve as a competitive source of electrical energy for enhancing Ghana’s energy security and socio-economic development for her to attain middle income as purported by political policies.DOI: http://dx.doi.org/10.5755/j01.erem.60.2.1109

  13. Development on Guidance of Cyber Security Exercise for the Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyundoo [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2016-10-15

    Cyber threats and attacks are increasing rapidly against infrastructure including energy and utilities industry over the world. Because of lack of human resource and incident response system to prevent or defend increased cyber threats, many governments and major national infrastructures perform cyber security exercises to improve capabilities of cyber security incident response. Accordingly there are exponential growth in the number of cyber security exercises over the past decade with the trend expecting to accelerate in the coming years. Even though there were many cyber security exercises in the Nuclear Facilities, this exercise was first which focused on mitigation and recovery of the system of the Nuclear Facility against cyber incident. So many insufficient items were deduced such as absence of a procedure for mitigation and recovery of cyber incident. These procedures should be developed and established through 3rd phase of Cyber Security Plan (CSP) and other technical complement actions under regulatory body’s guidance. Also developed and existed procedures should be regularly performed to make cyber incident response team and related people rapidly response against cyber incident through exercises or other training. The insufficient items come from the exercise should be reflected to developed and existed procedures by periods.

  14. Development of an Efficient Meso- scale Multi-phase Flow Solver in Nuclear Applications

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Taehun [City Univ. (CUNY), NY (United States)

    2015-10-20

    The proposed research aims at formulating a predictive high-order Lattice Boltzmann Equation for multi-phase flows relevant to nuclear energy related application - namely, saturated and sub-cooled boiling in reactors, and liquid- liquid mixing and extraction for fuel cycle separation. An efficient flow solver will be developed based on the Finite Element based Lattice Boltzmann Method (FE- LBM), accounting for phase-change heat transfer and capable of treating multiple phases over length scales from the submicron to the meter. A thermal LBM will be developed in order to handle adjustable Prandtl number, arbitrary specific heat ratio, a wide range of temperature variations, better numerical stability during liquid-vapor phase change, and full thermo-hydrodynamic consistency. Two-phase FE-LBM will be extended to liquid–liquid–gas multi-phase flows for application to high-fidelity simulations building up from the meso-scale up to the equipment sub-component scale. While several relevant applications exist, the initial applications for demonstration of the efficient methods to be developed as part of this project include numerical investigations of Critical Heat Flux (CHF) phenomena in nuclear reactor fuel bundles, and liquid-liquid mixing and interfacial area generation for liquid-liquid separations. In addition, targeted experiments will be conducted for validation of this advanced multi-phase model.

  15. Developing the User Experience for a Next Generation Nuclear Fuel Cycle Simulator (NGFCS)

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, Paul H. [Univ. of Wisconsin, Madison, WI (United States); Schneider, Erich [Univ. of Texas, Austin, TX (United States); Pascucci, Valerio [Univ. of Utah, Salt Lake City, UT (United States); Livnat, Yarden [Univ. of Utah, Salt Lake City, UT (United States); Hiromoto, Robert [Univ. of Idaho, Moscow, ID (United States); Scopatz, Anthony [Univ. of Wisconsin, Madison, WI (United States); Brossard, Dominique [Univ. of Wisconsin, Madison, WI (United States); Scheufele, Dietram [Univ. of Wisconsin, Madison, WI (United States)

    2017-07-30

    This project made substantial progress on its original aim for providing a modern user experience for nuclear fuel cycle analysis while also creating a robust and functional next- generation fuel cycle simulator. The Cyclus kernel experienced a dramatic clari cation of its interfaces and data model, becoming a full- edged agent-based framework, with strong support for third party developers of novel archetypes. The most important contribution of this project to the the development of Cyclus was the introduction of tools to facilitate archetype development. These include automated code generation of routine archetype components, metadata annotations to provide re ection and rich description of each data member's purpose, and mechanisms for input validation and output of complex data. A comprehensive social science investigation of decision makers' interests in nuclear fuel cycles, and speci cally their interests in nuclear fuel cycle simulators (NFCSs) as tools for understanding nuclear fuel cycle options, was conducted. This included document review and analysis, stakeholder interviews, and a survey of decision makers. This information was used to study the role of visualization formats and features in communicating information about nuclear fuel cycles. A exible and user-friendly tool was developed for building Cyclus analysis models, featuring a drag-and-drop interface and automatic input form generation for novel archetypes. Cycic allows users to design fuel cycles from arbitrary collections of facilities for the rst time, with mechanisms that contribute to consistency within that fuel cycle. Interacting with some of the metadata capabilities introduced in the above-mentioned tools to support archetype development, Cycic also automates the generation of user input forms for novel archetypes with little to no special knowledge required by the archetype developers. Translation of the fundamental metrics of Cyclus into more interesting quantities is

  16. Analysis of safety information for nuclear power plants and development of source term estimation program

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Tae Woon; Choi, Seong Soo; Park, Jin Hee [Atomic Creative Technology, Taejon (Korea, Republic of)

    1999-12-15

    Current CARE(Computerized Advisory System for Radiological Emergency) in KINS(Korea Institute of Nuclear Safety) has no STES(Source Term Estimation System) which links between SIDS(Safety Information Display System) and FADAS(Following Accident Dose Assessment System). So in this study, STES is under development. STES system is the system that estimates the source term based on the safety information provided by SIDS. Estimated source term is given to FADAS as an input for estimation of environmental effect of radiation. Through this first year project STES for the Kori 3,4 and Younggwang 1,2 has been developed. Since there is no CARE for Wolsong(PHWR) plants yet, CARE for Wolsong is under construction. The safety parameters are selected and the safety information display screens and the alarm logic for plant status change are developed for Wolsong Unit 2 based on the design documents for CANDU plants.

  17. Development of an ultrasonic imaging system for the inspection of nuclear reactor pressure vessels. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Becker, F.L.; Crow, V.L.; Davis, T.J.; Doctor, S.R.; Hildebrand, B.P.; Lemon, D.K.; Posakony, G.J.

    1979-10-01

    The development of an experimental model of an ultrasonic linear array system for the inspection of weldments in nuclear reactor pressure vessels is described. The imaging system is designed to operate in both pulse echo and holographic modes of operation. The system utilizes a sequentially pulsed, phase steered linear array to develop pulse echo images and a line focused illumination transducer in conjunction with a linear receiver array to develop holographic reconstructed images. The results recorded from the computer-based system demonstrate the capability of array technology. Excellent results from both the pulse echo and holographic modes of operation have been achieved. Pulse echo images of flaws in weldments are displayed in B-scan, C-scan, or isometric presentations. Reconstruction of the phase or holographic images are compared with pulse echo results and demonstrate the enhancement potential for the holographic procedure.

  18. Development of Web-Based Common Cause Failure (CCF) Database Module for Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hyun-Gyo; Hwang, Seok-Won; Shin, Tae-young [Korea Hydro and Nuclear Power Co. Ltd., Daejeon (Korea, Republic of)

    2015-05-15

    Probabilistic safety assessment (PSA) has been used to identify risk vulnerabilities and derive the safety improvement measures from construction to operation stages of nuclear power plants. In addition, risk insights from PSA can be applied to improve the designs and operation requirements of plants. However, reliability analysis methods for quantitative PSA evaluation have essentially inherent uncertainties, and it may create a distorted risk profiles because of the differences among the PSA models, plant designs, and operation status. Therefore, it is important to ensure the quality of the PSA model so that analysts identify design vulnerabilities and utilize risk information. Especially, the common cause failure (CCF) has been pointed out as one of major issues to be able to cause the uncertainty related to the PSA analysis methods and data because CCF has a large influence on the PSA results. Organization for economic cooperation and development /nuclear energy agent (OECD/NEA) has implemented an international common cause failure data exchange (ICDE) project for the CCF quality assurance through the development of the detailed analysis methodologies and data sharing. However, Korea Hydro and Nuclear Power company (KHNP) does not have the basis for the data gathering and analysis for CCF analyses. In case of methodology, the Alpha Factor parameter estimation, which can analyze uncertainties and estimate an interface factor (Impact Vector) with an ease, is ready to be applied rather than the Multi Greek Letter (MGL) method. This article summarizes the development of the plant-specific CCF database (DB) module considering the raw data collection and the analysis procedure based on the CCF parameter calculation method of ICDE. Although the portion affected by CCF in the PSA model is quite a large, the development efforts of the tools to collect and analyze data were insufficient. Currently, KHNP intends to improve PSA quality and ensure CCF data reliability by

  19. Development of Mechanical Sealing and Laser Welding Technology to Instrument Thermocouple for Nuclear Fuel Test Rod

    Energy Technology Data Exchange (ETDEWEB)

    Joung, Chang-Young; Ahn, Sung-Ho; Hong, Jin-Tae; Kim, Ka-Hye; Huh, Sung-Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    Zircaloy-4 of the nuclear fuel test rod, AISI 316L of the mechanical sealing parts, and the MI (mineral insulated) cable at a thermocouple instrumentation are hetero-metals, and are difficult to weld to dissimilar materials. Therefore, a mechanical sealing method to instrument the thermocouple should be conducted using two kinds of sealing process as follows: One is a mechanical sealing process using Swagelok, which is composed of sealing components that consists of an end-cap, a seal tube, a compression ring and a Swagelok nut. The other is a laser welding process used to join a seal tube, and an MI cable, which are made of the same material. The mechanical sealing process should be sealed up with the mechanical contact compressed by the strength forced between a seal tube and an end-cap, and the laser welding process should be conducted to have no defects on the sealing area between a seal tube and an MI cable. Therefore, the mechanical sealing and laser welding techniques need to be developed to accurately measure the centerline temperature of the nuclear fuel test rod in an experimental reactor. The mechanical sealing and laser welding tests were conducted to develop the thermocouple instrumentation techniques for the nuclear fuel test rod. The optimum torque value of a Swagelok nut to seal the mechanical sealing part between the end-cap and seal tube was established through various torque tests using a torque wrench. The optimum laser welding conditions to seal the welding part between a seal tube and an MI cable were obtained through various welding tests using a laser welding system.

  20. Development of Design Information Template for Nuclear Power Plants for Electromagnetic Pulse (EMP) Effect Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Minyi; Ryu, Hosan; Ye, Songhae; Lee, Euijong [KNHP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    An electromagnetic pulse (EMP) is a transient electromagnetic shock wave that has powerful electric and magnetic fields that can destroy electronic equipment. It is generally well-known that EMPs can cause the malfunction and disorder of electronic equipment and serious damages to electric power systems and communication networks. Research is being carried out to protect nuclear power plants (NPPs) from EMP threats. Penetration routes of EMPs can be roughly categorized into two groups, radioactivity and conductivity. The radioactive effect refers to an impact transmitted to the ground from high-altitude electromagnetic pulses (HEMP). Such an impact may affect target equipment through the point of entry (POE) of the concrete structure of an NPP. The conductive effect refers to induced voltage or current coupled to the NPPs cable structure. The induced voltage and current affect the target equipment via connected cables. All these factors must be considered when taking into account EMP effect analysis for NPPs. To examine all factors, it is necessary to fully understand the schemes of NPPs. This paper presents a four type design information template that can be used to analyze the EMP effect in operating nuclear power plants. In order to analyze of the effects of EMPs on operating NPPs, we must consider both the conductive and radioactive effects on the target (system, equipment, structure). For these reasons, not only the equipment information, but also the information about the structure and the external penetration will be required. We are developing a design information template for robust nuclear design information acquisition. We expect to develop a block diagram on the basis of the template.

  1. Developments of integrity evaluation technology for pressurized components in nuclear power plant and IT based integrity evaluation system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; Choi, Jae Boong; Shim, Do Jun [Sungkyunkwan Univ., Seoul (Korea, Republic of)] (and others)

    2003-03-15

    The objective of this research is to develop an efficient evaluation technology and to investigate applicability of newly-developed technology, such as internet-based cyber platform, to operating power plants. Development of efficient evaluation systems for Nuclear Power Plant components, based on structural integrity assessment techniques, are increasingly demanded for safe operation with the increasing operating period of Nuclear Power Plants. The following five topics are covered in this project: development of assessment method for wall-thinned nuclear piping based on pipe test; development of structural integrity program for steam generator tubes with cracks of various shape; development of fatigue life evaluation system for mam components of NPP; development of internet-based cyber platform and integrity program for primary components of NPP; effect of aging on strength of dissimilar welds.

  2. 田湾核电站核安全文化建设%The Cultivation and Development of Nuclear Safety Culture in Tianwan Nuclear Power Station

    Institute of Scientific and Technical Information of China (English)

    毛志新

    2015-01-01

    The cultivation and development of nuclear safety culture in Tianwan Nuclear Power Station go through four stages: cognition, promotion, continuous improvement and commitment to excellence, establishing a Tianwan characteristic nuclear safety culture, which is carrying through traits of a healthy nuclear safety culture, building an image of the Tianwan people, insisting on zero tolerance, and strengthen the sense of responsibility. In addition, following PDCA circulation pattern, regular safety culture assessmentin nuclear power station is carried out, areas to be improved are identified, closed-loop control is achieved. After years of efforts, with the abstraction of the safety concept, safety culture mechanism and system construction, safety culture training and publicity, etc. In Tianwan nuclear power station, the station has obtained remarkable results, ensured excellence of nuclear safety culture, so that the level of nuclear safety and operating performance are improved.%田湾核电核安全文化建设经过了认知、提升、持续改进和追求卓越4个阶段,形成了"贯彻健康核安全文化特征,打造中核田湾人形象,坚持零容忍,强化责任心"的具有田湾特色的核安全文化.另外,做到遵循PDCA循环模式,评估活动常态化,定期对电站的核安全文化进行评估,找出待改进的领域,从而改进提升,达到闭环控制的目的.田湾核电站多年在安全理念提炼、安全文化制度和体系建设、安全文化培训和宣传等方面不断努力,保证卓越的核安全文化落地,从而提升核电站的核安全水平和运行业绩.

  3. Japanese experiences in human resources development in the nuclear fields and proposal on procedure of the 1st seminar

    Energy Technology Data Exchange (ETDEWEB)

    Murao, Yoshio [Japan Atomic Energy Research Inst., Tokyo (Japan)

    2000-12-01

    The Atomic Energy Basic Act was enforced in 1956. The law prescribed establishment of the Atomic Energy Commission (establishment of the Nuclear Safety Commission was added in 1978), definition of administrative bodies for nuclear fuel materials and reactors and radiation protection, and necessary regulatory laws. The law also prescribed establishment of a national nuclear center for R and D and human resources development, i.e. Japan Atomic Energy Research Institute (JAERI) was established in 1956. The Nuclear Technology and Education Center (NuTEC) RI school was opened in 1958. Establishments of Power Reactor and Nuclear Fuel Development Corporation and National Institute of Radiological Science were in 1956 and 1957, respectively. In universities, nuclear facilities were constructed for supplying young human resources based on decision by Ministry of Education after 1961. The foundation of Japan Atomic Energy Power Co. (JAPCO) was in 1957. In the NuTEC, a variety of training courses had been prepared and carried out to meet the requirements of the nuclear community. Many leaders and experts had been produced and they worked for development of nuclear infrastructure in Japan. International training programs were started in 1985 and the experiences were applied for helping Asian countries to develop the manpower for nuclear infrastructure. Japanese safety actions for nuclear technology had strongly depended on that of USA. Therefore, much efforts on safety evaluation and phenomenological understanding are necessary in Japan. Recent tendency is changed from development-minded approach to safety-minded approach and is focused more on efforts to get public consent on nuclear energy. However, Japanese experiences will be useful for developing human resources in other countries. The NuTEC of JAERI will operate the seminar once a year. The seminar will be implemented; to get mutual recognition on present status and problems of regional countries by gathering information

  4. Nuclear power in the Baltic Sea region: the history of emergence and the political and economic features of its development

    Directory of Open Access Journals (Sweden)

    Kretinin G.

    2013-01-01

    Full Text Available This article focuses on the development of peaceful nuclear power. The author draws attention to the fact that nuclear power is a rather young branch of national economy. However, over recent decades, it has already seen rises and falls, and a number of states have had tragic experiences of nuclear emergencies. Nevertheless, many countries — including the three Baltic States of Estonia, Latvia and Lithuania — express a strong interest in development, generation, and application of nuclear power. In the Baltic States, nuclear power dates back to the Soviet times, but its development was suspended pursuant to the EU regulations (the Ignalina NPP. Lithuania, Latvia, and Estonia have been striving for energy independence from Russia — the principal supplier of energy carriers to these countries. For a long time, the three Baltic States have been proclaiming their unanimity on the general European path of development. However, the reality proved to be different. The touchstone for achieving common goals was the idea of constructing a new NPP at the site of the closed Ignalina NPP. The author concludes that the joint construction of a new NPP is quite questionable. When it comes to politics, each of the three Baltic States is ready to build its own NPP. Thus, the development of nuclear power in the Baltic Sea region requires joint coordinated actions independent of any bloc-inspired interests of the states involved. Moreover, this success may prove sustainable if the actions are based on innovative decisions and modern technologies.

  5. Development of a computational database for probabilistic safety assessment of nuclear research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Macedo, Vagner S.; Oliveira, Patricia S. Pagetti de; Andrade, Delvonei Alves de, E-mail: vagner.macedo@usp.br, E-mail: patricia@ipen.br, E-mail: delvonei@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    The objective of this work is to describe the database being developed at IPEN - CNEN / SP for application in the Probabilistic Safety Assessment of nuclear research reactors. The database can be accessed by means of a computational program installed in the corporate computer network, named IPEN Intranet, and this access will be allowed only to professionals previously registered. Data updating, editing and searching tasks will be controlled by a system administrator according to IPEN Intranet security rules. The logical model and the physical structure of the database can be represented by an Entity Relationship Model, which is based on the operational routines performed by IPEN - CNEN / SP users. The web application designed for the management of the database is named PSADB. It is being developed with MySQL database software and PHP programming language is being used. Data stored in this database are divided into modules that refer to technical specifications, operating history, maintenance history and failure events associated with the main components of the nuclear facilities. (author)

  6. Development of a Functional Platform for System Reliability Monitoring of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Ming; Zhang, Zhijian; Yoshikawa, Hidekazu [Harbin Engineering University, Harbin (China)

    2014-08-15

    This paper presents MFM builder, a platform based on Multilevel Flow Modeling (MFM), which provides a graphical interface for modeling functions of complex artificial systems such as nuclear power plant with emphasizing the designed purposes of systems. Several algorithms based on MFM have been developed for dynamic system reliability analysis, fault diagnosis and quantitative software reliability analysis. A Reliability Monitoring System (RMS) of PWR nuclear power plant was developed by integrating above algorithms. Experiments by connecting RMS with a full scale PWR simulator showed that it took 16 seconds for RMS calculating the reliability changes over time of safety-related systems according to given system configurations in the 31 days by one computer run. The proposed reliability monitoring system can be used not only offline as a reliability analysis tool to assist the plant maintenance staffs in maintenance plan making, but also online as a operator support system to assist the operators in Main Control Room (MCR) in their various tasks such as configuration management, fault diagnosis and operational decision making.

  7. Development of a Nuclear Hydrogen Production System by Dimethyl Ether (DME) Steam Reforming and Related Technology

    Science.gov (United States)

    Fukushima, Kimichika; Oota, Hiroyuki; Yamada, Kazuya; Makino, Shinichi; Yagyu, Motoshige; Ikeda, Tatsumi; Asayama, Masahiro; Ogawa, Takashi; Yoshino, Masato

    Targeting a hydrogen production system using heat produced by a nuclear reactor at about 300°C, we are developing a dimethyl ether (DME) steam reformer and hydrogen purification systems as well as catalysts for DME reforming. The use of heat from a nuclear reactor suppresses the CO2 concentration change in the atmosphere. In our developments, a catalyst, consisting of mixed oxides, produced hydrogen at a rate of about 1.9 Nm3/h per catalyst volume (m3) at about 300°C. Subsequently, the DME steam reformer achieved a hydrogen production rate of approximately, at least, 1.4 Nm3/h at about 300°C, by absorbing heat from the supplied steam. The aforementioned hydrogen production system via DME steam reforming is to be demonstrated using a thermal power plant. DME steam reforming by using waste heat and the utilization of the produced hydrogen within a combined cycle power plant can reduce fuel consumption, for instance, by about 17% compared to the case of direct DME combustion. The total system, with the use of DME, was compared with the methane case. If necessary, the byproduced CO2 may be injected into coal seams, increasing CH4 production via the substitution of CO2 for CH4 on coal, where CO2 adsorption is expected to be stronger than the CH4 adsorption.

  8. Development of melt dilute technology for disposition of aluminum based spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Swift, W.F. [Nuclear Material Management Division Westinghouse Savannah River Company, Savannah River Site Building 707-C, Aiken, SC 29808 (United States)

    2002-07-01

    The US Department of Energy (DOE) has for many years had a program for receipt and disposition of spent nuclear fuels of US origin from research reactors around the world. The research reactor spent nuclear fuel that consists of aluminum alloy composition has historically been returned to the Savannah River Site (SRS) and dispositioned via chemical reprocessing. In 1995, the DOE evaluated a number of alternatives to chemical reprocessing. In 2000, the DOE selected the melt-dilute alternative as the primary disposition path and direct disposal as the backup path. The melt-dilute technology has been developed from lab-scale demonstration up through the construction of a pilot-scale facility. The pilot-scale L-Area Experimental Facility (LEF) has been constructed and is ready for operation. The LEF will be used primarily, to confirm laboratory research on zeolite media for off- gas trapping and remote operability. Favorable results from the LEF are expected to lead to final design of the production melt-dilute facility identified as the Treatment and Storage Facility (TSF). This paper will describe the melt-dilute process and provide a status of the program development. (author)

  9. Next Generation Nuclear Plant Materials Research and Development Program Plan, Revision 4

    Energy Technology Data Exchange (ETDEWEB)

    G.O. Hayner; R.L. Bratton; R.E. Mizia; W.E. Windes; W.R. Corwin; T.D. Burchell; C.E. Duty; Y. Katoh; J.W. Klett; T.E. McGreevy; R.K. Nanstad; W. Ren; P.L. Rittenhouse; L.L. Snead; R.W. Swindeman; D.F. Wlson

    2007-09-01

    DOE has selected the High Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 950°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed reactor and use low-enriched uranium, TRISO-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Some of the general and administrative aspects of the R&D Plan include: • Expand American Society of Mechanical Engineers (ASME) Codes and American Society for Testing and Materials (ASTM) Standards in support of the NGNP Materials R&D Program. • Define and develop inspection needs and the procedures for those inspections. • Support selected university materials related R&D activities that would be of direct benefit to the NGNP Project. • Support international materials related collaboration activities through the DOE sponsored Generation IV International Forum (GIF) Materials and Components (M&C) Project Management Board (PMB). • Support document review activities through the Materials Review Committee (MRC) or other suitable forum.

  10. Development of a Multi-Arm Mobile Robot for Nuclear Decommissioning Tasks

    Directory of Open Access Journals (Sweden)

    Mohamed J. Bakari

    2007-12-01

    Full Text Available This paper concerns the design of a two-arm mobile delivery platform for application within nuclear decommissioning tasks. The adoption of the human arm as a model of manoeuvrability, scale and dexterity is the starting point for operation of two seven-function arms within the context of nuclear decommissioning tasks, the selection of hardware and its integration, and the development of suitable control methods. The forward and inverse kinematics for the manipulators are derived and the proposed software architecture identified to control the movements of the arm joints and the performance of selected decommissioning tasks. We discuss the adoption of a BROKK demolition machine as a mobile platform and the integration with its hydraulic system to operate the two seven-function manipulators separately. The paper examines the modelling and development of a real-time control method using Proportional-Integral-Derivative (PID and Proportional-Integral-Plus (PIP control algorithms in the host computer with National Instruments functions and tools to control the manipulators and obtain feedback through wireless communication. Finally we consider the application of a third party device, such as a personal mobile phone, and its interface with LabVIEW software in order to operate the robot arms remotely.

  11. Development of neutron measurement in high gamma field using new nuclear emulsion

    Energy Technology Data Exchange (ETDEWEB)

    Kawarabayashi, J.; Ishihara, K.; Takagi, K.; Tomita, H.; Iguchi, T.; Naka, T.; Morishima, K. [Nagoya Univ., Nagoya, Aichi (Japan); Maeda, S. [Japan Atomic Energy Agency, Narita-cho, Oarai-machi, Ibaragi (Japan)

    2011-07-01

    To precisely measure the neutron emissions from a spent fuel assembly of a fast breeder reactor, we formed nuclear emulsions based on a non-sensitized Oscillation Project with Emulsion tracking Apparatus (OPERA) film with AgBr grain sizes of 60, 90, and 160 nm. The efficiency for {sup 252}Cf neutron detection of the new emulsion was calculated to be 0.7 x 10{sup -4}, which corresponded to an energy range from 0.3 to 2 MeV and was consistent with a preliminary estimate based on experimental results. The sensitivity of the new emulsion was also experimentally estimated by irradiating with 565 keV and 14 MeV neutrons. The emulsion with an AgBr grain size of 60 nm had the lowest sensitivity among the above three emulsions but was still sensitive enough to detect protons. Furthermore, the experimental data suggested that there was a threshold linear energy transfer of 15 keV/{mu}m for the new emulsion, below which no silver clusters developed. Further development of nuclear emulsion with an AgBr grain size of a few tens of nanometers will be the next stage of the present study. (authors)

  12. Development of a Multi-Arm Mobile Robot for Nuclear Decommissioning Tasks

    Directory of Open Access Journals (Sweden)

    Mohamed J. Bakari

    2008-11-01

    Full Text Available This paper concerns the design of a two-arm mobile delivery platform for application within nuclear decommissioning tasks. The adoption of the human arm as a model of manoeuvrability, scale and dexterity is the starting point for operation of two seven-function arms within the context of nuclear decommissioning tasks, the selection of hardware and its integration, and the development of suitable control methods. The forward and inverse kinematics for the manipulators are derived and the proposed software architecture identified to control the movements of the arm joints and the performance of selected decommissioning tasks. We discuss the adoption of a BROKK demolition machine as a mobile platform and the integration with its hydraulic system to operate the two seven-function manipulators separately. The paper examines the modelling and development of a real-time control method using Proportional-Integral-Derivative (PID and Proportional-Integral-Plus (PIP control algorithms in the host computer with National Instruments functions and tools to control the manipulators and obtain feedback through wireless communication. Finally we consider the application of a third party device, such as a personal mobile phone, and its interface with LabVIEW software in order to operate the robot arms remotely.

  13. Development of Advanced Nuclide Separation and Recovery Methods using Ion-Exchanhge Techniques in Nuclear Backend

    Science.gov (United States)

    Miura, Hitoshi

    The development of compact separation and recovery methods using selective ion-exchange techniques is very important for the reprocessing and high-level liquid wastes (HLLWs) treatment in the nuclear backend field. The selective nuclide separation techniques are effective for the volume reduction of wastes and the utilization of valuable nuclides, and expected for the construction of advanced nuclear fuel cycle system and the rationalization of waste treatment. In order to accomplish the selective nuclide separation, the design and synthesis of novel adsorbents are essential for the development of compact and precise separation processes. The present paper deals with the preparation of highly functional and selective hybrid microcapsules enclosing nano-adsorbents in the alginate gel polymer matrices by sol-gel methods, their characterization and the clarification of selective adsorption properties by batch and column methods. The selective separation of Cs, Pd and Re in real HLLW was further accomplished by using novel microcapsules, and an advanced nuclide separation system was proposed by the combination of selective processes using microcapsules.

  14. Development of a Leading Performance Indicator from Operational Experience and Resilience in a Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Pamela F. Nelson

    2016-02-01

    Full Text Available The development of operational performance indicators is of utmost importance for nuclear power plants, since they measure, track, and trend plant operation. Leading indicators are ideal for reducing the likelihood of consequential events. This paper describes the operational data analysis of the information contained in the Corrective Action Program. The methodology considers human error and organizational factors because of their large contribution to consequential events. The results include a tool developed from the data to be used for the identification, prediction, and reduction of the likelihood of significant consequential events. This tool is based on the resilience curve that was built from the plant's operational data. The stress is described by the number of unresolved condition reports. The strain is represented by the number of preventive maintenance tasks and other periodic work activities (i.e., baseline activities, as well as, closing open corrective actions assigned to different departments to resolve the condition reports (i.e., corrective action workload. Beyond the identified resilience threshold, the stress exceeds the station's ability to operate successfully and there is an increased likelihood that a consequential event will occur. A performance indicator is proposed to reduce the likelihood of consequential events at nuclear power plants.

  15. Develop an piezoelectric sensing based on SHM system for nuclear dry storage system

    Science.gov (United States)

    Ma, Linlin; Lin, Bin; Sun, Xiaoyi; Howden, Stephen; Yu, Lingyu

    2016-04-01

    In US, there are over 1482 dry cask storage system (DCSS) in use storing 57,807 fuel assemblies. Monitoring is necessary to determine and predict the degradation state of the systems and structures. Therefore, nondestructive monitoring is in urgent need and must be integrated into the fuel cycle to quantify the "state of health" for the safe operation of nuclear power plants (NPP) and radioactive waste storage systems (RWSS). Innovative approaches are desired to evaluate the degradation and damage of used fuel containers under extended storage. Structural health monitoring (SHM) is an emerging technology that uses in-situ sensory system to perform rapid nondestructive detection of structural damage as well as long-term integrity monitoring. It has been extensively studied in aerospace engineering over the past two decades. This paper presents the development of a SHM and damage detection methodology based on piezoelectric sensors technologies for steel canisters in nuclear dry cask storage system. Durability and survivability of piezoelectric sensors under temperature influence are first investigated in this work by evaluating sensor capacitance and electromechanical admittance. Toward damage detection, the PES are configured in pitch catch setup to transmit and receive guided waves in plate-like structures. When the inspected structure has damage such as a surface defect, the incident guided waves will be reflected or scattered resulting in changes in the wave measurements. Sparse array algorithm is developed and implemented using multiple sensors to image the structure. The sparse array algorithm is also evaluated at elevated temperature.

  16. SOME RECENT TECHNOLOGY DEVELOPMENTS FROM THE UK'S NATIONAL NUCLEAR LABORATORY TO ENABLE HAZARD CHARACTERISATION FOR NUCLEAR DECOMMISSIONING APPLICATIONS

    Energy Technology Data Exchange (ETDEWEB)

    Farfan, E.; Foley, T.

    2010-02-11

    Under its programme of self investment Internal Research and Development (IR&D), the UK's National Nuclear Laboratory (NNL) is addressing the requirement for development in technology to enable hazard characterisation for nuclear decommissioning applications. Three such examples are described here: (1) RadBall developed by the NNL (patent pending) is a deployable baseball-sized radiation mapping device which can, from a single location, locate and quantify radiation hazards. RadBall offers a means to collect information regarding the magnitude and distribution of radiation in a given cell, glovebox or room to support the development of a safe, cost effective decontamination strategy. RadBall requires no electrical supplies and is relatively small, making it easy to be deployed and used to map radiation hazards in hard to reach areas. Recent work conducted in partnership with the Savannah River National Laboratory (SRNL) is presented. (2) HiRAD (patent pending) has been developed by the NNL in partnership with Tracerco Ltd (UK). HiRAD is a real-time, remotely deployed, radiation detection device designed to operate in elevated levels of radiation (i.e. thousands and tens of thousands of Gray) as seen in parts of the nuclear industry. Like the RadBall technology, the HiRAD system does not require any electrical components, the small dimensions and flexibility of the device allow it to be positioned in difficult to access areas (such as pipe work). HiRAD can be deployed as a single detector, a chain, or as an array giving the ability to monitor large process areas. Results during the development and deployment of the technology are presented. (3) Wireless Sensor Network is a NNL supported development project led by the University of Manchester (UK) in partnership with Oxford University (UK). The project is concerned with the development of wireless sensor network technology to enable the underwater deployment and communication of miniaturised probes allowing pond

  17. SOME RECENT TECHNOLOGY DEVELOPMENTS FROM THE UK'S NATIONAL NUCLEAR LABORATORY TO ENABLE HAZARD CHARACTERISATION FOR NUCLEAR DECOMMISSIONING APPLICATIONS

    Energy Technology Data Exchange (ETDEWEB)

    Farfan, E.; Foley, T.

    2010-02-11

    Under its programme of self investment Internal Research and Development (IR&D), the UK's National Nuclear Laboratory (NNL) is addressing the requirement for development in technology to enable hazard characterisation for nuclear decommissioning applications. Three such examples are described here: (1) RadBall developed by the NNL (patent pending) is a deployable baseball-sized radiation mapping device which can, from a single location, locate and quantify radiation hazards. RadBall offers a means to collect information regarding the magnitude and distribution of radiation in a given cell, glovebox or room to support the development of a safe, cost effective decontamination strategy. RadBall requires no electrical supplies and is relatively small, making it easy to be deployed and used to map radiation hazards in hard to reach areas. Recent work conducted in partnership with the Savannah River National Laboratory (SRNL) is presented. (2) HiRAD (patent pending) has been developed by the NNL in partnership with Tracerco Ltd (UK). HiRAD is a real-time, remotely deployed, radiation detection device designed to operate in elevated levels of radiation (i.e. thousands and tens of thousands of Gray) as seen in parts of the nuclear industry. Like the RadBall technology, the HiRAD system does not require any electrical components, the small dimensions and flexibility of the device allow it to be positioned in difficult to access areas (such as pipe work). HiRAD can be deployed as a single detector, a chain, or as an array giving the ability to monitor large process areas. Results during the development and deployment of the technology are presented. (3) Wireless Sensor Network is a NNL supported development project led by the University of Manchester (UK) in partnership with Oxford University (UK). The project is concerned with the development of wireless sensor network technology to enable the underwater deployment and communication of miniaturised probes allowing pond

  18. Indonesia's present status and needs of human resource development in nuclear field

    Energy Technology Data Exchange (ETDEWEB)

    Ruslan, Jeni; Sagala, F.P. [National Nuclear Energy Agency of Indonesia (Indonesia)

    2000-12-01

    BATAN, started out as a governmental committee established in 1954, has a new organizational structure, based on Presidential Decree of 1998. BATAN has developed its researches in almost practically all-nuclear fields. The situation in Indonesia has been much influenced by the economic crisis, which still being faced by Indonesia. BATAN's strategic planning is described in four areas, those are: 1. Basic human needs, 2. Energy, natural resources and environment, 3. Industry, 4. Socio-cultural and institution. Priority has been given to fulfill, as well as to promote agriculture, health and the industry related to people's welfare, which may develop and improve the immediate needs of the people. In the meantime, we have made considerable investments in manpower development in anticipation of the introduction of nuclear power. BATAN, as of September 1999, has 3889 employees, 26 % of them have bachelor degree, 6 % hold master degrees, and only 2% hold doctoral degree, a total of 34 % employees with university education. Others 11 % have either non-vocational or vocational education beyond High School. The rest of 55 % have high school education or lower, they are administrative clerks (25 %) or technicians (30 %). In the human resources development, BATAN's Education and Training Center, in collaboration with some universities and other national/international institutions, is managing education and training programs for employees. To date, there are 43 BATAN employees studying in various universities in Japan, while another 42 employees are studying in six different countries. Research and Development that have more direct impact to the community will become a priority in the coming years. Without undermining the importance of basic research in advanced fields, we will expect to have more research on application to optimize utilization of research reactors and related facilities for the benefit of both the energy and non-energy sectors. (Tanaka, Y.)

  19. Spent nuclear fuel retrieval system fuel handling development testing. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Jackson, D.R.; Meeuwsen, P.V.

    1997-09-01

    Fuel handling development testing was performed in support of the Fuel Retrieval System (FRS) Sub-Project, a subtask of the Spent Nuclear Fuel Project at the Hanford Site in Richland, Washington. The FRS will be used to retrieve and repackage K-Basin Spent Nuclear Fuel (SNF) currently stored in old K-Plant storage basins. The FRS is required to retrieve full fuel canisters from the basin, clean the fuel elements inside the canister to remove excessive uranium corrosion products (or sludge), remove the contents from the canisters and sort the resulting debris, scrap, and fuel for repackaging. The fuel elements and scrap will be collected in fuel storage and scrap baskets in preparation for loading into a multi canister overpack (MCO), while the debris is loaded into a debris bin and disposed of as solid waste. This report describes fuel handling development testing performed from May 1, 1997 through the end of August 1997. Testing during this period was mainly focused on performance of a Schilling Robotic Systems` Conan manipulator used to simulate a custom designed version, labeled Konan, being fabricated for K-Basin deployment. In addition to the manipulator, the camera viewing system, process table layout, and fuel handling processes were evaluated. The Conan test manipulator was installed and fully functional for testing in early 1997. Formal testing began May 1. The purposes of fuel handling development testing were to provide proof of concept and criteria, optimize equipment layout, initialize the process definition, and identify special needs/tools and required design changes to support development of the performance specification. The test program was set up to accomplish these objectives through cold (non-radiological) development testing using simulated and prototype equipment.

  20. INPRO Activities on Development of Advanced Tools to Support Judgment Aggregation for Comparative Evaluation of Nuclear Energy Systems

    Directory of Open Access Journals (Sweden)

    V. Kuznetsov

    2015-01-01

    Full Text Available This paper presents first results of the INPRO Collaborative Project on Key Indicators for Innovative Nuclear Energy Systems, which has the objective to develop guidance and tools for comparative evaluation of the status, prospects, benefits, and risks associated with development of innovative nuclear technologies for a more distant future. Presented results illustrate expedience of application of the multicriteria decision analysis methods, which are able to provide the added value to comparative assessment of nuclear energy systems. First, the paper presents a short review of the multicriteria decision analysis methods appropriate to support judgment aggregation within comparative evaluations of nuclear energy systems based on key indicators and highlights the methodology to perform such assessments. Second, a set of key indicators elaborated in the INPRO Collaborative Project on Global Architecture of Innovative Nuclear Energy Systems Based on Thermal and Fast Reactors Including a Closed Fuel Cycle (GAINS were evaluated for comparative evaluation of nuclear energy system evolution scenarios. Third, a numerical example is presented of application of the selected key indicators, methods, and tools for judgment aggregation in comparative assessment of the GAINS nuclear energy systems.

  1. Joint research project to develop a training course or nuclear policy decision makers and planners in developing countries between KAERI and IAEA

    Energy Technology Data Exchange (ETDEWEB)

    Lee, E. J.; Suh, I. S.; Lee, H. Y. and others

    2000-12-01

    KAERI developed training course curricula on nuclear power policy and planning for decision makers and planners in developing countries under the assistance of the IAEA. It was utilized two IAEA staff members and a Korean consultation group were utilized for the development of curricula. Curriculum consists of training objectives, training contents in modular basis, detailed contents of each training module, training setting, training duration, session hours, and entry requirements of audience. One is workshop on nuclear energy policy for high-level decision makers in developing countries. The other is training course on nuclear power planning and project management for middle level managers in developing countries. The textbook in English will be printed by the end of February in 2001. Developed curricula will be implemented for Vietnam high level nuclear decision makers, middle level managers in developing countries and north Korea nuclear high level decision makers in 2001. These training courses' curricula and textbook will be utilized as basic technical documents to promote the national nuclear bilateral technical cooperation programs with Morocco, Egypt, Bangladesh, Indonesia, Ukraine, etc.

  2. Analysis of Inland Nuclear Power Development Situation%内陆核电发展形势分析

    Institute of Scientific and Technical Information of China (English)

    赵小辉; 邹树梁; 刘永

    2012-01-01

    核电作为一种安全、清洁和高效的能源,适应了经济发展与环境保护的要求,是能源战略的选择方向。虽然日本福岛核电站事故对世界核电发展有一定的影响,但核电发展不能因之却步。从世界核电发展趋势和我国经济需要来看,内陆核电发展是一种趋势:世界内陆核电已占50%以上;核电安全性进一步提升;内陆中部崛起战略的能源需求和能源结构优化。湖南桃花江核电项目将开启我国内陆核电序幕,并将推动我国核电的健康发展。%Nuclear Power as a safe,clean and efficient energy, adapted to the requirements of economic development and enviro- mantal protection, is the direction choice of energy strategy. Although Japan Fukushima accident has some impact on the nuclear power development in the world,it could not be deterred. Inland nuclear power development is a trend for the world development and China' s economic needs:Inland nuclear power has accounted for more than 50% of the world;Nuclear security has been further improved;Ener- gy demand and energy structurt of uprising strategy in landlocked central areas have been optimized. Taohuajiang nuclear power project in Hunan will open a prelude to China inland nuclear power and promote the healthy development of China' s nuclear power.

  3. Development of technology-neutral safety requirements for the regulation of future nuclear power reactors: Back to basics

    Energy Technology Data Exchange (ETDEWEB)

    Tronea, Madalina, E-mail: madalina.tronea@gmail.co [Faculty of Physics, University of Bucharest (Romania)

    2011-03-15

    This paper explores the current trends as regards the development of technology-neutral safety requirements to be used in the regulation of future nuclear power reactors and the role of the quantitative safety goals in the design of reactor safety systems. The use of the recommendations of the International Commission on Radiological Protection (ICRP) on protection against potential exposure could form the basis of a technology-neutral framework for safety requirements on new reactor designs and could contribute to international harmonisation of nuclear safety assessment practices as part of the licensing processes for future nuclear power plants.

  4. Development of a High- Brightness, Quasi- Monoenergetic Neutron Source at LLNL for Nuclear Physics Applications

    Science.gov (United States)

    Johnson, M. S.; Anderson, S. G.; Bleuel, D.; Fitsos, P. J.; Gibson, D.; Hall, J. M.; Marsh, R.; Rusnak, B.

    2016-09-01

    Lawrence Livermore National Laboratory is developing a high-brightness, quasi-monoenergetic neutron source. The intensity of the neutron source is expected to be 1011 n/s/sr with energies between 7 MeV and 10 MeV at 5% bandwidth at 0-degrees. This energy region is important for the study of neutron-induced reactions, nuclear astrophysics, and nuclear structure. For example, for neutrons between 1 and 10 MeV, the capturing states are below the GDR in many nuclei and the dominant reactions are compound and direct capture. The intensity and energy selection of the source makes it appealing for measurements of sparse targets at specific energies. We will present an array of nuclear physics measurements that will benefit from this source. The source is also of interest to generating activated targets for decay-out studies or for target production for other reaction-based measurements, e.g. fusion-evaporation reactions. Other usage examples include practical applications for imaging of very dense objects such as machine parts. For this presentation, we will discuss our method to use (d,n) production reaction on deuterium in a windowless gas target system. This approach is required because of the large power of the 7 MeV, 300 μA deuteron beams. We will discuss our facility and its capabilities. This work performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344.

  5. Development of a Probabilistic Flood Hazard Assessment (PFHA) for the nuclear safety

    Science.gov (United States)

    Ben Daoued, Amine; Guimier, Laurent; Hamdi, Yasser; Duluc, Claire-Marie; Rebour, Vincent

    2016-04-01

    The purpose of this study is to lay the basis for a probabilistic evaluation of flood hazard (PFHA). Probabilistic assessment of external floods has become a current topic of interest to the nuclear scientific community. Probabilistic approaches complement deterministic approaches by exploring a set of scenarios and associating a probability to each of them. These approaches aim to identify all possible failure scenarios, combining their probability, in order to cover all possible sources of risk. They are based on the distributions of initiators and/or the variables caracterizing these initiators. The PFHA can characterize the water level for example at defined point of interest in the nuclear site. This probabilistic flood hazard characterization takes into account all the phenomena that can contribute to the flooding of the site. The main steps of the PFHA are: i) identification of flooding phenomena (rains, sea water level, etc.) and screening of relevant phenomena to the nuclear site, ii) identification and probabilization of parameters associated to selected flooding phenomena, iii) spreading of the probabilized parameters from the source to the point of interest in the site, v) obtaining hazard curves and aggregation of flooding phenomena contributions at the point of interest taking into account the uncertainties. Within this framework, the methodology of the PFHA has been developed for several flooding phenomena (rain and/or sea water level, etc.) and then implemented and tested with a simplified case study. In the same logic, our study is still in progress to take into account other flooding phenomena and to carry out more case studies.

  6. Development of a Method for Quantifying the Reliability of Nuclear Safety-Related Software

    Energy Technology Data Exchange (ETDEWEB)

    Yi Zhang; Michael W. Golay

    2003-10-01

    The work of our project is intended to help introducing digital technologies into nuclear power into nuclear power plant safety related software applications. In our project we utilize a combination of modern software engineering methods: design process discipline and feedback, formal methods, automated computer aided software engineering tools, automatic code generation, and extensive feasible structure flow path testing to improve software quality. The tactics include ensuring that the software structure is kept simple, permitting routine testing during design development, permitting extensive finished product testing in the input data space of most likely service and using test-based Bayesian updating to estimate the probability that a random software input will encounter an error upon execution. From the results obtained the software reliability can be both improved and its value estimated. Hopefully our success in the project's work can aid the transition of the nuclear enterprise into the modern information world. In our work, we have been using the proprietary sample software, the digital Signal Validation Algorithm (SVA), provided by Westinghouse. Also our work is being done with their collaboration. The SVA software is used for selecting the plant instrumentation signal set which is to be used as the input the digital Plant Protection System (PPS). This is the system that automatically decides whether to trip the reactor. In our work, we are using -001 computer assisted software engineering (CASE) tool of Hamilton Technologies Inc. This tool is capable of stating the syntactic structure of a program reflecting its state requirements, logical functions and data structure.

  7. Development of novel extractants for the recycle system of transuranium elements from nuclear fuel-3

    Energy Technology Data Exchange (ETDEWEB)

    Goto, Masahiro [Kyushu Univ., Fukuoka (Japan). Faculty of Engineering

    1998-03-01

    Novel bi-functional extractants which have two organophosphorus moieties in the molecular structure were designed and synthesized for the recycle system of transuranium elements using liquid-liquid extraction. The separation efficiency and extraction ability of the newly synthesized extractants were investigated for rare earth metals. The new extractants have an high extractability to the rare earth metals compared with that of commercially available phosphorus extractants. The obtained results suggest that the extraction and separation abilities are highly sensitive to the molecular structure of the spacer connecting the two functional phosphorus groups. The results of thermodynamic analysis for extraction equilibrium indicate that the entropy effect on the extraction is one of the key factors to enhance the selectivity in the rare earth extractions. Furthermore, a computer analysis was carried out to evaluate the extraction properties for the extraction of rare earth metals by the bi-functional extractants. It is demonstrated that the new concept to connect some functional moieties with a spacer is very useful and is a promising method to develop new extractants for the treatment of nuclear fuel. We have proposed a novel molecular imprinting technique for the treatment of waste nuclear solutions. A surface-imprinting resin was prepared by an emulsion polymerization using a novel organophosphorus extractant as a host monomer for rare earth metals. The host monomer which has amphiphilic nature forms a complex with a rare earth metal ion at the interface, and the complex remains as it is. After the matrix is polymerized, the coordination structure is `imprinted` at the resin interface. The imprinted resins exhibited a high adsorption selectivity to the target Dy ion. We believe that the novel imprint techniques will be useful for the treatment of nuclear waste water. (J.P.N.)

  8. Development of a standard methodology for optimizing remote visual display for nuclear-maintenance tasks

    Energy Technology Data Exchange (ETDEWEB)

    Clarke, M.M.; Garin, J.; Preston-Anderson, A.

    1981-01-01

    The aim of the present study is to develop a methodology for optimizing remote viewing systems for a fuel recycle facility (HEF) being designed at Oak Ridge National Laboratory (ORNL). An important feature of this design involves the Remotex concept: advanced servo-controlled master/slave manipulators, with remote television viewing, will totally replace direct human contact with the radioactive environment. Therefore, the design of optimal viewing conditions is a critical component of the overall man/machine system. A methodology has been developed for optimizing remote visual displays for nuclear maintenance tasks. The usefulness of this approach has been demonstrated by preliminary specification of optimal closed circuit TV systems for such tasks.

  9. Development of accident management technology and computer codes -A study for nuclear safety improvement-

    Energy Technology Data Exchange (ETDEWEB)

    Park, Chang Kyu; Jae, Moo Sung; Jo, Young Gyun; Park, Rae Jun; Kim, Jae Hwan; Ha, Jae Ju; Kang, Dae Il; Choi, Sun Young; Kim, Si Hwan [Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)

    1994-07-01

    We have surveyed new technologies and research results for the accident management of nuclear power plants. And, based on the concept of using the existing plant capabilities for accident management, both in-vessel and ex-vessel strategies were identified and analyzed. When assessing accident management strategies, their effectiveness, adverse effects, and their feasibility must be considered. We have developed a framework for assessing the strategies with these factors in mind. We have applied the developed framework to assessing the strategies, including the likelihood that the operator correctly diagnoses the situation and successfully implements the strategies. Finally, the cavity flooding strategy was assessed by applying it to the station blackout sequence, which have been identified as one of the major contributors to risk at the reference plant. The thermohydraulic analyses with sensitivity calculations have been performed using MAAP 4 computer code. (Author).

  10. Development of a drone equipped with optimized sensors for nuclear and radiological risk characterization

    Energy Technology Data Exchange (ETDEWEB)

    Boudergui, K.; Carrel, F.; Domenech, T. [CEA LIST LCAE, CEA Saclay, 91191 Gif-sur-Yvette Cedex (France); Guenard, N.; Poli, J. P. [CEA LIST LIMA, CEA Saclay, 91191 Gif-sur-Yvette Cedex (France); Ravet, A. [CEA LIST LISA, CEA Fontenay-aux-Roses, 92265 Fontenay-aux-Roses Cedex (France); Schoepff, V.; Woo, R. [CEA LIST LCAE, CEA Saclay, 91191 Gif-sur-Yvette Cedex (France)

    2011-07-01

    The MOBISIC project, funded by the Systematic Paris-Region cluster, is being developed in the context of local crisis (attack bombing in urban environment, in confined space such as an underground train tunnel etc.) or specific event securing (soccer world cup, political meeting etc.). It consists in conceiving, developing and experimenting a mobile, modular ('plug and play') and multi-sensors securing system. In this project, CEA LIST has suggested different solutions for nuclear risks detection and identification. It results in embedding a CZT sensor and a gamma camera in an indoor drone. This article first presents the different modifications carried out on the UAV and different sensors, and focuses then on the experimental performances. (authors)

  11. Development of Students' Metacognitive Strategies In Science Learning Regarding Nuclear Energy

    Science.gov (United States)

    Siriuthen, Warawun; Yuenyong, Chokchai

    2010-07-01

    This research aimed to develop 48 Grade 10 students' learning process and metacognitive strategies in the `Nuclear Energy' topic through the Science, Technology and Society (STS) approach. The STS teaching approach consists of five stages: identification of social issues, identification of potential solutions, need for knowledge, decision-making, and socialization. he data were analyzed through rubric score of learning process and metacognitive strategies, which consists of five strategies: Recalling, Planning, Monitoring and Maintaining, Evaluating, and Relating. The findings revealed that most students used learning process in a high level. They performed a very low level in almost all of the metacognitive strategies. The factors potentially impeded their development of awareness about learning process and metacognitive strategies were characteristics of content and students, learning processes, and student habit.

  12. Isoforms of the nuclear envelope protein Nurim are differentially expressed during heart development in mice.

    Science.gov (United States)

    Zhang, Wan; Bai, Tianyu; Zhang, Shuai; Xu, Shiqiang; Chen, Hengling; Li, Chenhong

    2017-09-05

    To date, transcript variants of the nuclear envelope protein Nurim and their expression profiles in mice have never been elucidated. In this study, we determined that the primary Nurim variant a was abundantly expressed in mouse heart, liver, spleen and kidney. The protein level of isoform a is initiated at an early stage of heart formation and demonstrated a significant increase in expression throughout embryonic heart development. Interestingly, Nurim b is also up-regulated from E12.5 to E18.5 in different individuals. Our research represents the first report on alternative splicing variants of mouse Nurim and their differential expression profile during embryonic development. These studies suggest a potential role for Nurim in early heart morphogenesis and should help further elucidate the function of Nurim. Copyright © 2017. Published by Elsevier B.V.

  13. Issues and future direction of thermal-hydraulics research and development in nuclear power reactors

    Energy Technology Data Exchange (ETDEWEB)

    Saha, P., E-mail: pradip.saha@ge.com [GE Hitachi Nuclear Energy, Wilmington, NC (United States); Aksan, N. [GRNSPG Group, University of Pisa (Italy); Andersen, J. [GE Hitachi Nuclear Energy, Wilmington, NC (United States); Yan, J. [Westinghouse Electric Co., Columbia, SC (United States); Simoneau, J.P. [AREVA, Lyon (France); Leung, L. [Atomic Energy of Canada Ltd., Chalk River, Ontario (Canada); Bertrand, F. [CEA, DEN, DER, F-13108 Saint-Paul-Lez-Durance (France); Aoto, K.; Kamide, H. [Japan Atomic Energy Agency, Chiyoda-ku, Tokyo (Japan)

    2013-11-15

    The paper archives the proceedings of an expert panel discussion on the issues and future direction of thermal-hydraulic research and development in nuclear power reactors held at the NURETH-14 conference in Toronto, Canada, in September 2011. Thermal-hydraulic issues related to both operating and advanced reactors are presented. Advances in thermal-hydraulics have significantly improved the performance of operating reactors. Further thermal-hydraulics research and development is continuing in both experimental and computational areas for operating reactors, reactors under construction or ready for near-term deployment, and advanced Generation-IV reactors. As the computing power increases, the fine-scale multi-physics computational models, coupled with the systems analysis code, are expected to provide answers to many challenging problems in both operating and advanced reactor designs.

  14. Development of maintenance equipment for nuclear material fabrication equipment in a highly active hot cell

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-09-01

    This report presents the development of a maintenance system for a highly contaminated nuclear material handling equipment at a hot-cell. This maintenance system has mainly three subsystems - a gamma-radiation measurement module for detecting a gamma-radiation level and identifying its distribution in-situ, a dry-type decontamination device for cleaning up contaminated particles, and a maintenance chamber for isolating contaminated equipment. The mechanical design considerations, controller, capabilities and remote operation and manipulation of the maintenance system are described. Such subsystems developed were installed and tested in the IMEF (Irradiated Material Examination Facility) M6 hot-cell after mock-up tests and performed their specific tasks successfully.

  15. Prospects for development of an innovative water-cooled nuclear reactor for supercritical parameters of coolant

    Science.gov (United States)

    Kalyakin, S. G.; Kirillov, P. L.; Baranaev, Yu. D.; Glebov, A. P.; Bogoslovskaya, G. P.; Nikitenko, M. P.; Makhin, V. M.; Churkin, A. N.

    2014-08-01

    The state of nuclear power engineering as of February 1, 2014 and the accomplished elaborations of a supercritical-pressure water-cooled reactor are briefly reviewed, and the prospects of this new project are discussed based on this review. The new project rests on the experience gained from the development and operation of stationary water-cooled reactor plants, including VVERs, PWRs, BWRs, and RBMKs (their combined service life totals more than 15 000 reactor-years), and long-term experience gained around the world with operation of thermal power plants the turbines of which are driven by steam with supercritical and ultrasupercritical parameters. The advantages of such reactor are pointed out together with the scientific-technical problems that need to be solved during further development of such installations. The knowledge gained for the last decade makes it possible to refine the concept and to commence the work on designing an experimental small-capacity reactor.

  16. Development of a nuclear reactor control system simulator using virtual instruments

    Energy Technology Data Exchange (ETDEWEB)

    Pinto, Antonio Juscelino; Mesquita, Amir Zacarias; Lameiras, Fernando Soares, E-mail: ajp@cdtn.b, E-mail: amir@cdtn.b, E-mail: fsl@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    The International Atomic Energy Agency recommends the use of safety and friendly interfaces for monitoring and controlling the operational parameters of the nuclear reactors. This article describes a digital system being developed to simulate the behavior of the operating parameters using virtual instruments. The control objective is to bring the reactor power from its source level (mW) to a full power (kW). It is intended for education of basic reactor neutronic and thermohydraulic principles such as the multiplication factor, criticality, reactivity, period, delayed neutron, control by rods, fuel and coolant temperatures, power, etc. The 250 kW IPR-R1 TRIGA research reactor at Nuclear Technology Development Centre - CDTN was used as reference. TRIGA reactors, developed by General Atomics (GA), are the most widely used research reactor in the world. The simulator system is being developed using the LabVIEW (Laboratory Virtual Instruments Engineering Workbench) software, considering the modern concept of virtual instruments (VI's) using electronic processor and visual interface in video monitor. The main purpose of the system is to provide training tools for instructors and students, allowing navigating by user-friendly operator interface and monitoring tendencies of the operational variables. It will be an interactive tool for training and teaching and could be used to predict the reactor behavior. Some scenarios are presented to demonstrate that it is possible to know the behavior of some variables from knowledge of input parameters. The TRIGA simulator system will allow the study of parameters, which affect the reactor operation, without the necessity of using the facility. (author)

  17. Application of objective provision tree to development of standard review plan for sodium-cooled fast reactor nuclear design

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Moo-Hoon; Suh, Namduk; Choi, Yongwon; Shin, Andong [Korea Institute of Nuclear Safety, Daejon (Korea, Republic of)

    2016-06-15

    A systematic methodology was developed for the standard review plan for sodium-cooled fast reactor nuclear design. The process is first to develop an objective provision tree of sodium-cooled fast reactor for the reactivity control safety function. The provision tree is generally developed by designer to confirm whether the design satisfies the defense-in-depth concept. Then applicability of the current standard review plan of nuclear design for light water reactor to sodium-cooled fast reactor was evaluated and complemented by the developed objective provision tree.

  18. [Development of a job exposure matrix for the epidemiological follow-up of workers in the French nuclear industry.

    OpenAIRE

    Guseva Canu, Irina; Molina, G; Goldberg, Marcel; Collomb, P.; David, J. -C.; Perez, P.; Paquet, F.; Tirmarche, Margot

    2008-01-01

    International audience; BACKGROUND: A pilot study was carried out in the AREVA NC Pierrelatte nuclear facility in order to investigate a possible carcinogenic effect of internal radiation exposure among nuclear workers in France. The objective of this study was to develop a method for retrospective reconstruction of the occupational exposure to internal radiation from uranium and associated chemical exposures. METHODS: A plant- and period-specific job exposure matrix (JEM) was designed. Job g...

  19. Research and development for decontamination system of spent resin in Hanbit Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Sung, Gi Hong [Dept. of Nuclear Engineering, Chosun University, Gwangju (Korea, Republic of)

    2015-12-15

    When reactor coolant leaks occur due to cracks of a steam generator tube, radioactive materials contained in the primary cooling water in nuclear power plant are forced out toward the secondary systems. At this time the secondary water purification resin in the ion exchange resin tower of the steam generator blowdown system is contaminated by the radioactivity of the leaked radioactive materials, so we pack this in special containers and store temporarily because we could not dispose it by ourselves. If steam generator tube leakage occurs, it produces contaminated spent resins annually about 5,000-7,000 liters. This may increase the amount of nuclear waste productions, a disposal working cost and a unit price of generating electricity in the plant. For this reasons, it is required to develop a decontamination process technique for reducing the radioactive level of these resins enough to handle by the self-disposal method. In this research, First, Investigated the structure and properties of the ion exchange resin used in a steam generator blowdown system. Second, Checked for a occurrence status of contaminated spent resin and a disposal technology. Third, identified the chemical characteristics of the waste radionuclides of the spent resin, and examined ionic bonding and separation mechanism of radioactive nuclear species and a spent resin. Finally, we carried out the decontamination experiment using chemicals, ultrasound, microbubbles, supercritical carbon dioxide to process these spent resin. In the case of the spent resin decontamination method using chemicals, the higher the concentration of the drug decontamination efficiency was higher. In the ultrasound method, foreign matter of the spent resin was removed and was found that the level of radioactivity is below of the MDA. In the microbubbles method, we found that the concentration of the radioactivity decreased after the experiment, so it can be used to the decontamination process of the spent resin. In

  20. Developing hyperpolarized krypton-83 for nuclear magnetic resonance spectroscopy and magnetic resonance imaging

    Science.gov (United States)

    Cleveland, Zackary I.

    This dissertation discusses the production of highly nonequilibrium nuclear spin polarization, referred to as hyperpolarization or hp, in the nuclear spin I = 9/2 noble gas isotope krypton-83 using spin exchange optical pumping (SEOP). This nonequilibrium polarization yields nuclear magnetic resonance (NMR) signals that are enhanced three or more orders of magnitude above those of thermally polarized krypton and enables experiments that would otherwise be impossible. Krypton-83 possesses a nuclear electric quadrupole moment that dominates the longitudinal (T1) relaxation due to coupling of the quadrupole moment to fluctuating electric field gradients generated by distortions to the spherical symmetry of the electronic environment. Relaxation slows polarization buildup and limits the maximum signal intensity but makes krypton-83 a sensitive probe of its environment. The gas-phase krypton-83 longitudinal relaxation rate increases linearly with total gas density due to binary collisions. Density independent relaxation, caused by the formation of krypton-krypton van der Waals molecules and surface adsorption, also contributes to the observed rate. Buffer gases suppress van der Waals molecule mediated relaxation by breaking apart the weakly bound krypton dimers. Surface relaxation is gas composition independent and therefore more difficult to suppress. However, this relaxation mechanism makes hp krypton-83 sensitive to important surface properties including surface-to-volume ratio, surface chemistry, and surface temperature. The presence of surfaces with high krypton adsorption affinities (i.e. hydrophobic surfaces) accelerates the relaxation times and can produce T1 contrast in hp krypton-83 magnetic resonance imaging (MRI). Tobacco smoke deposited on surfaces generates strong T1 contrast allowing the observation of smoke deposition with spatial resolution. Conversely, water adsorption on surfaces significantly lengths the T1 times due competitive surface adsorption

  1. The nuclear orphan receptor COUP-TFII is required for limb and skeletal muscle development.

    Science.gov (United States)

    Lee, Christopher T; Li, Luoping; Takamoto, Norio; Martin, James F; Demayo, Francesco J; Tsai, Ming-Jer; Tsai, Sophia Y

    2004-12-01

    The nuclear orphan receptor COUP-TFII is widely expressed in multiple tissues and organs throughout embryonic development, suggesting that COUP-TFII is involved in multiple aspects of embryogenesis. Because of the early embryonic lethality of COUP-TFII knockout mice, the role of COUP-TFII during limb development has not been determined. COUP-TFII is expressed in lateral plate mesoderm of the early embryo prior to limb bud formation. In addition, COUP-TFII is also expressed in the somites and skeletal muscle precursors of the limbs. Therefore, in order to study the potential role of COUP-TFII in limb and skeletal muscle development, we bypassed the early embryonic lethality of the COUP-TFII mutant by using two methods. First, embryonic chimera analysis has revealed an obligatory role for COUP-TFII in limb bud outgrowth since mutant cells are unable to contribute to the distally growing limb mesenchyme. Second, we used a conditional-knockout approach to ablate COUP-TFII specifically in the limbs. Loss of COUP-TFII in the limbs leads to hypoplastic skeletal muscle development, as well as shorter limbs. Taken together, our results demonstrate that COUP-TFII plays an early role in limb bud outgrowth but not limb bud initiation. Also, COUP-TFII is required for appropriate development of the skeletal musculature of developing limbs.

  2. Energy security, sustainable development, which place for the Nuclear in the world?; Securite energetique, developpement durable, quelle place pour le nucleaire dans le monde?

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    Facing the increase of the energy consumption and the necessity of the greenhouse gases emission decrease, the authors define the role of the nuclear energy in a policy of a sustainable development. They recall the leadership part of the France in the nuclear research and development and the channel of the nuclear production. The second part of the paper proposes sheets of countries energy policy and nuclear program situation: USA, Europe, Russian, China and India. (A.L.B.)

  3. [Development of the software package of the nuclear medicine data processor for education and research].

    Science.gov (United States)

    Maeda, Hisato; Yamaki, Noriyasu; Azuma, Makoto

    2012-01-01

    The objective of this study was to develop a personal computer-based nuclear medicine data processor for education and research in the field of nuclear medicine. We call this software package "Prominence Processor" (PP). Windows of Microsoft Corporation was used as the operating system of this PP, which have 1024 × 768 image resolution and various 63 applications classified into 6 groups. The accuracy was examined for a lot of applications of the PP. For example, in the FBP reconstruction application, there was visually no difference in the image quality as a result of comparing two SPECT images obtained from the PP and GMS-5500A (Toshiba). Moreover, Normalized MSE between both images showed 0.0003. Therefore the high processing accuracy of the FBP reconstruction application was proven as well as other applications. The PP can be used in an arbitrary place if the software package is installed in note PC. Therefore the PP is used to lecture and to practice on an educational site and used for the purpose of the research of the radiological technologist on a clinical site etc. widely now.

  4. Development of irradiation capabilities to address the challenges of the nuclear industry

    Energy Technology Data Exchange (ETDEWEB)

    Leay, L. [The University of Manchester, Dalton Cumbrian Facility, Westlakes Science and Technology Park, Moor Row, Cumbria CA24 3HA (United Kingdom); The University of Manchester, School of Electrical and Electronic Engineering, Oxford Road, Manchester M13 9PL (United Kingdom); Bower, W. [The University of Manchester, Dalton Cumbrian Facility, Westlakes Science and Technology Park, Moor Row, Cumbria CA24 3HA (United Kingdom); The University of Manchester, School of Earth, Atmospheric and Environmental Sciences, Oxford Road, Manchester M13 9PL (United Kingdom); Horne, G.; Wady, P.; Baidak, A. [The University of Manchester, Dalton Cumbrian Facility, Westlakes Science and Technology Park, Moor Row, Cumbria CA24 3HA (United Kingdom); The University of Manchester, School of Chemistry, Oxford Road, Manchester M13 9PL (United Kingdom); Pottinger, M. [The University of Manchester, Dalton Cumbrian Facility, Westlakes Science and Technology Park, Moor Row, Cumbria CA24 3HA (United Kingdom); The University of Manchester, School of Electrical and Electronic Engineering, Oxford Road, Manchester M13 9PL (United Kingdom); Nancekievill, M. [The University of Manchester, School of Electrical and Electronic Engineering, Oxford Road, Manchester M13 9PL (United Kingdom); Smith, A.D. [The University of Manchester, Dalton Cumbrian Facility, Westlakes Science and Technology Park, Moor Row, Cumbria CA24 3HA (United Kingdom); Watson, S. [The University of Manchester, Dalton Cumbrian Facility, Westlakes Science and Technology Park, Moor Row, Cumbria CA24 3HA (United Kingdom); The University of Manchester, School of Electrical and Electronic Engineering, Oxford Road, Manchester M13 9PL (United Kingdom); Green, P.R. [The University of Manchester, School of Electrical and Electronic Engineering, Oxford Road, Manchester M13 9PL (United Kingdom); and others

    2015-01-15

    With the announcement of the U.K. new nuclear build and the requirement to decommission old facilities, researchers require bespoke facilities to undertake experiments to inform decision making. This paper describes development of The University of Manchester’s Dalton Cumbrian Facility, a custom built research environment which incorporates a 5 MV tandem ion accelerator as well as a self-shielded {sup 60}Co irradiator. The ion accelerator allows the investigation into the radiolytic consequences of various charged particles, including protons, alpha particles and a variety of heavier (metal and nonmetal) ions, while the {sup 60}Co irradiator allows the effects of gamma radiation to be studied. Some examples of work carried out at the facility are presented to demonstrate how this equipment can improve our mechanistic understanding of various aspects of the deleterious effects of radiation in the nuclear industry. These examples include applications in waste storage and reprocessing as well as geological storage and novel surveying techniques. The outlook for future research is also discussed.

  5. The development of a nuclear accident risk information system(NARIS)

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Jong Tae; Jung, Won Dea [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2002-03-01

    The computerized system, NARIS(Nuclear Accident Risk Information System) was developed in order to support the estimation of health effects and the establishment the effective risk reduction strategies. Using the system, we can analyze the distribution of health effects easily by displaying the results on the digital map of the site. Also, the thematic mapping allows the diverse analysis of the distribution of the health effects.The NARIS can be used in the emergency operation facilities in order to analyze the distribution of the health effects resulting from the severe accidents of a nuclear power plant. Also, the rapid analysis of the health effect is possible by storing the health effect results in the form of a database. Therefore, the staffs of the emergency operation facilities can establish the rapid and effective emergency response strategies. The module for the optimization of the costs and benefits and the decision making support will be added. The technical support for the establishment of the optimum and effective emergency response strategies will be possible using this system. 23 figs., 1 tab. (Author)

  6. A comparison of nuclear thermal rocket development cost and schedule for piloted missions to Mars

    Science.gov (United States)

    Clark, John S.; Borowski, Stanley K.; Sefcik, Robert J.; Miller, Thomas J.

    1993-01-01

    In Fiscal Year 1992, NASA led a team, including DOE, universities, and industry, that evaluated various schedule and cost scenarios for development of nuclear thermal rocket propulsion systems for piloted Mars exploration. This paper summarizes the results of two of these studies: (1) a so-called 'Fast Track' approach, that would result in technology readiness level 6 (TRL-6-system ground testing complete) by the year 2000, and (2) a slower program that results in TRL-6 by 2006. Both scenarios included a concurrent engineering approach. Costs and schedules for the two scenarios are compared. In addition to the six-year schedule delay, the TRL-6 in 2006 scenario is estimated to increase the cost of the program from $4.7 billion to $5.8 billion (in real-year dollars). On the positive side, the technical program should be better, since nuclear testing of fuel elements may be possible prior to concept down-select, resulting in a more informed decision.

  7. Design criteria development for the structural stability of nuclear waste repository

    Energy Technology Data Exchange (ETDEWEB)

    Yun, C. H. [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Yu, T. S. [Daewoo Engineering Company, Sungnam (Korea, Republic of); Ko, H. M. [Seoul National Univ., Seoul (Korea, Republic of)] (and others)

    1990-11-15

    The objective of the present project is to develop design criteria for the structural stability of rock cavity for the underground repository are defined, according to which detailed descriptions for design methodologies, design stages and stability analysis of the cavity are made. The proposed criteria can be used as a guide for the preparation of design codes which are to be established as the site condition and technical emplacement procedure are fixed. The present report first reviews basic safety requirements and criteria of the underground disposal of nuclear wastes for the establishment of design concepts and stability analysis of the rock cavity. Important factors for the design are also described by considering characteristics of the wastes and underground facilities. The present project has investigated technical aspects on the design of underground structures based on the currently established underground construction technologies, and presented a proposal for design criteria for the structural stability of the nuclear waste repository. The proposed criteria consist of general provisions, geological exploration, rock classification, design process and methods, supporting system, analyses and instrumentation.

  8. Development of high gradient laser wakefield accelerators towards nuclear detection applications at LBNL

    Energy Technology Data Exchange (ETDEWEB)

    Geddes, Cameron GR; Bruhwiler, David L.; Cary, John R.; Esarey, Eric H.; Gonsalves, Anthony J.; Lin, Chen; Cormier-Michel, Estelle; Matlis, Nicholas H.; Nakamura, Kei; Bakeman, Mike; Panasenko, Dmitriy; Plateau, Guillaume R.; Schroeder, Carl B.; Toth, Csaba; Leemans, Wim P.

    2008-09-08

    Compact high-energy linacs are important to applications including monochromatic gamma sources for nuclear material security applications. Recent laser wakefield accelerator experiments at LBNL demonstrated narrow energy spread beams, now with energies of up to 1 GeV in 3 cm using a plasma channel at low density. This demonstrates the production of GeV beams from devices much smaller than conventional linacs, and confirms the anticipated scaling of laser driven accelerators to GeV energies. Stable performance at 0.5 GeV was demonstrated. Experiments and simulations are in progress to control injection of particles into the wake and hence to improve beam quality and stability. Using plasma density gradients to control injection, stable beams at 1 MeV over days of operation, and with an order of magnitude lower absolute momentum spread than previously observed, have been demonstrated. New experiments are post-accelerating the beams from controlled injection experiments to increase beam quality and stability. Thomson scattering from such beams is being developed to provide collimated multi-MeV monoenergetic gamma sources for security applications from compact devices. Such sources can reduce dose to target and increase accuracy for applications including photofission and nuclear resonance fluorescence.

  9. Web design and development for centralize area radiation monitoring system in Malaysian Nuclear Agency

    Science.gov (United States)

    Ibrahim, Maslina Mohd; Yussup, Nolida; Haris, Mohd Fauzi; Soh @ Shaari, Syirrazie Che; Azman, Azraf; Razalim, Faizal Azrin B. Abdul; Yapp, Raymond; Hasim, Harzawardi; Aslan, Mohd Dzul Aiman

    2017-01-01

    One of the applications for radiation detector is area monitoring which is crucial for safety especially at a place where radiation source is involved. An environmental radiation monitoring system is a professional system that combines flexibility and ease of use for data collection and monitoring. Nowadays, with the growth of technology, devices and equipment can be connected to the network and Internet to enable online data acquisition. This technology enables data from the area monitoring devices to be transmitted to any place and location directly and faster. In Nuclear Malaysia, area radiation monitor devices are located at several selective locations such as laboratories and radiation facility. This system utilizes an Ethernet as a communication media for data acquisition of the area radiation levels from radiation detectors and stores the data at a server for recording and analysis. This paper discusses on the design and development of website that enable all user in Nuclear Malaysia to access and monitor the radiation level for each radiation detectors at real time online. The web design also included a query feature for history data from various locations online. The communication between the server's software and web server is discussed in detail in this paper.

  10. Capabilities Development for Transient Testing of Advanced Nuclear Fuels at TREAT

    Energy Technology Data Exchange (ETDEWEB)

    Woolstenhulme, N. E.; Baker, C. C.; Bess, J. D.; Davis, C. B.; Hill, C. M.; Housley, G. K.; Jensen, C. B.; Jerred, N. D.; O' Brien, R. C.; Snow, S. D.; Wachs, D. M.

    2016-09-01

    The TREAT facility is a unique capability at the Idaho National Laboratory currently being prepared for resumption of nuclear transient testing. Accordingly, designs for several transient irradiation tests are being pursued to enable development of advanced nuclear fuels and materials. In addition to the reactor itself, the foundation for TREAT’s capabilities also include a suite of irradiation vehicles and supporting infrastructure to provide the desired specimen boundary conditions while supporting a variety of instrumentation needs. The challenge of creating these vehicles, especially since many of the modern data needs were not historically addressed in TREAT experiment vehicles, has necessitated a sizeable engineering effort. This effort is currently underway and maturing rapidly. This paper summarizes the status, future plans, and rationale for TREAT experiment vehicle capabilities. Much of the current progress is focused around understanding and demonstrating the behavior of fuel design with enhanced accident tolerance in water-cooled reactors. Additionally, several related efforts are underway to facilitate transient testing in liquid sodium, inert gas, and steam environments. This paper discusses why such a variety of capabilities are needed, outlines plans to accomplish them, and describes the relationship between transient data needs and the irradiation hardware that will support the gathering of this information.

  11. Development of Causality Analyzer for Maintenance/Test Tasks in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Heo, Gyun Young; Oh, Kye Min; Kim, So Young; Kim, Tae Mi; Ahmed, Rizwan [KyungHee University, Yongin (Korea, Republic of)

    2010-02-15

    The purpose of this project is to propose a causality analyzer for maintenance/test tasks in nuclear power plants in terms of fault tree analysis and turbine cycle simulation for a secondary side. In nuclear power plants, a lot of efforts to reduce unanticipated trips caused by maintenance or tests have been conducted, so many of trip causalities in a primary side were eliminated. However, it is still difficult to effectively recognize the causalities for the tasks of maintenance/tests in a secondary side. This study, therefore, attempted to propose a methodology based on fault tree analysis and derate simulation, which is particularly applicable for a secondary side. Ultimately, it is possible to develop the guidelines to warn the vulnerability in the tasks by proactively providing the human errors from maintenance or tests. The products of this study is able to predict the enhancement of plant availability by correlating the human errors resulting from maintenance/tests with a various type of plant losses

  12. Developing a program to identify and track corrosion in nuclear plant raw water systems

    Energy Technology Data Exchange (ETDEWEB)

    Spires PE, G.V. [KTA - Tator Inc., Pittsburgh, Pennsylvania (United States); Pickles PE, S.B. [Senior Engineer, Ontario Power Generation, Ontario (Canada)

    2001-07-01

    Findings derived from a comprehensive plant performance survey at Ontario Power Generation's (OPG) nuclear units convinced management that it would be prudent to expand the ongoing power piping Flow Accelerated Corrosion (FAC) induced wall thinning base-lining and tracking program to encompass the raw cooling water systems as well. Such systems are subject to a distinctly different class of pipe wall thinning (PWT) mechanisms than the FAC that degrades high-energy power piping. This paper describes the PWT corrosion assessment and tracking program that has been developed and is currently being implemented by OPG for the raw cooling water (i.e., Service Water) systems within it's nuclear generating stations. Interim databases are used prior to initial inspection rounds to catalogue the prospective locations. For each piping system being surveyed, these interim databases include physical coordinates for the candidate locations, the type and wall thickness of the components comprising each location, ranking indications and recommended NDE methodologies as a function of the anticipated corrosion mechanisms. Rationales for assessing corrosion susceptibility and ranking prospective inspection sites are expounded by way of notations built into the database. (authors)

  13. Applied nuclear data research and development. Progress report, January 1-March 31, 1981

    Energy Technology Data Exchange (ETDEWEB)

    Baxman, C.I.; Young, P.G. (comps.)

    1981-07-01

    Activities of the Los Alamos Nuclear Data Group for January 1 through March 31, 1981, are described. Topics include: (1) peripheral effects in R-matrix theory; (2) Coulomb corrections in light nuclei; (3) new R-matrix analysis of reactions in the /sup 7/Li system; (4) variance-covariance analysis of n + Li reactions; (5) calculated charged-particle emission in the mass-90 region; (6) determination of deformed optical model parameters for neutron reactions on /sup 235/U and /sup 239/Pu; (7) calculation of excited state cross sections for actinide nuclei; (8) calculation of the prompt neutron spectrum and ..nu../sub p/ for the spontaneous fission of /sup 252/Cf; (9) international nuclear model codes comparison study; (10) an improved calculation of heating and radiation damage from neutron capture; (11) LMFBR cross-section production with MAX; (12) TRANSX development; (13) THOR calculations; (14) covariance processing; (15) analysis of charges for use of central computing facility; (16) S/sub n/ calculations for D/sub 2/O sphere; (17) integral data testing of ENDF/B fission-product data; (18) decay power comparisons using ENDF/B-IV and -V data in CINDER-10; (19) ENDF/B-V data testing and summary data; (20) SPEC5: code to produce multigroup spectra; and (21) calculation of H. B. Robinson-2 fuel isotopics and comparison with measurements. (WHK)

  14. Applications of nuclear physics

    Science.gov (United States)

    Hayes, A. C.

    2017-02-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applications of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.

  15. Globalisation of the nuclear fuel cycle - impact of developments on fuel management

    Energy Technology Data Exchange (ETDEWEB)

    Durpel, L. van den; Bertel, E. [OECD Nuclear Energy Agency, 92 - Issy-les-Moulineaux (France)

    2000-02-01

    Nuclear energy will have to cope more and more with a rapid changing environment due to economic competitive pressure and the deregulatory progress. In current economic environment, utilities will have to focus strongly on the reduction of their total generation costs, covering the fuel cycle costs, which are only partly under their control. Developments in the fuel cycle will be in the short-term rather evolutionary addressing the current needs of utilities. However, within the context of sustainable development and more and more inclusion of externalities in energy generation costs, more performing developments in the fuel cycle could become important and feasible. A life-cycle design approach of the fuel cycle will be requested in order to cover all factors in order to decrease significantly the nuclear energy generation cost to complete with other alternative fuels in the long-term. This paper will report on some of the trends one could distinguish in the fuel cycle with emphasis on cost reduction. OECD/NEA is currently conducting a study on the fuel cycle aiming to assess current and future nuclear fuel cycles according to the potential for further improvement of the full added-value chain of these cycles from a mainly technological and economic perspective including environmental and social considerations. (orig.) [German] Die Kernenergie wird sich mehr und mehr in einem Umfeld behaupten muessen, das durch schnelle Veraenderungen auf Grund des Wettbewerbsdrucks in der Wirtschaft und des Liberalisierungsprozesses gekennzeichnet ist. Im heutigen Wirtschaftsumfeld muessen sich die Energieversorgungsunternehmen hauptsaechlich auf die Senkung ihrer Stromerzeugungs-Gesamtkosten konzentrieren. Darunter fallen auch die Brennstoffkreislaufkosten, die sie nur zum Teil beeinflussen koennen. Kurzfristig gesehen, duerften die Entwicklungen im Brennstoffkreislauf eher evolutionaer verlaufen und den jeweiligen Beduerfnissen der EVUs entsprechen. Im Zusammenhang mit einer

  16. Development and application of the dynamic system doctor to nuclear reactor probabilistic risk assessments.

    Energy Technology Data Exchange (ETDEWEB)

    Kunsman, David Marvin; Aldemir, Tunc (Ohio State University); Rutt, Benjamin (Ohio State University); Metzroth, Kyle (Ohio State University); Catalyurek, Umit (Ohio State University); Denning, Richard (Ohio State University); Hakobyan, Aram (Ohio State University); Dunagan, Sean C.

    2008-05-01

    This LDRD project has produced a tool that makes probabilistic risk assessments (PRAs) of nuclear reactors - analyses which are very resource intensive - more efficient. PRAs of nuclear reactors are being increasingly relied on by the United States Nuclear Regulatory Commission (U.S.N.R.C.) for licensing decisions for current and advanced reactors. Yet, PRAs are produced much as they were 20 years ago. The work here applied a modern systems analysis technique to the accident progression analysis portion of the PRA; the technique was a system-independent multi-task computer driver routine. Initially, the objective of the work was to fuse the accident progression event tree (APET) portion of a PRA to the dynamic system doctor (DSD) created by Ohio State University. Instead, during the initial efforts, it was found that the DSD could be linked directly to a detailed accident progression phenomenological simulation code - the type on which APET construction and analysis relies, albeit indirectly - and thereby directly create and analyze the APET. The expanded DSD computational architecture and infrastructure that was created during this effort is called ADAPT (Analysis of Dynamic Accident Progression Trees). ADAPT is a system software infrastructure that supports execution and analysis of multiple dynamic event-tree simulations on distributed environments. A simulator abstraction layer was developed, and a generic driver was implemented for executing simulators on a distributed environment. As a demonstration of the use of the methodological tool, ADAPT was applied to quantify the likelihood of competing accident progression pathways occurring for a particular accident scenario in a particular reactor type using MELCOR, an integrated severe accident analysis code developed at Sandia. (ADAPT was intentionally created with flexibility, however, and is not limited to interacting with only one code. With minor coding changes to input files, ADAPT can be linked to other

  17. BWR Spent Nuclear Fuel Integrity Research and Development Survey for UKABWR Spent Fuel Interim Storage

    Energy Technology Data Exchange (ETDEWEB)

    Bevard, Bruce Balkcom [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Mertyurek, Ugur [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Belles, Randy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Scaglione, John M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-10-01

    The objective of this report is to identify issues and support documentation and identify and detail existing research on spent fuel dry storage; provide information to support potential R&D for the UKABWR (United Kingdom Advanced Boiling Water Reactor) Spent Fuel Interim Storage (SFIS) Pre-Construction Safety Report; and support development of answers to questions developed by the regulator. Where there are gaps or insufficient data, Oak Ridge National Laboratory (ORNL) has summarized the research planned to provide the necessary data along with the schedule for the research, if known. Spent nuclear fuel (SNF) from nuclear power plants has historically been stored on site (wet) in spent fuel pools pending ultimate disposition. Nuclear power users (countries, utilities, vendors) are developing a suite of options and set of supporting analyses that will enable future informed choices about how best to manage these materials. As part of that effort, they are beginning to lay the groundwork for implementing longer-term interim storage of the SNF and the Greater Than Class C (CTCC) waste (dry). Deploying dry storage will require a number of technical issues to be addressed. For the past 4-5 years, ORNL has been supporting the U.S. Department of Energy (DOE) in identifying these key technical issues, managing the collection of data to be used in issue resolution, and identifying gaps in the needed data. During this effort, ORNL subject matter experts (SMEs) have become expert in understanding what information is publicly available and what gaps in data remain. To ensure the safety of the spent fuel under normal and frequent conditions of wet and subsequent dry storage, intact fuel must be shown to: 1.Maintain fuel cladding integrity; 2.Maintain its geometry for cooling, shielding, and subcriticality; 3.Maintain retrievability, and damaged fuel with pinhole or hairline cracks must be shown not to degrade further. Where PWR (pressurized water reactor) information is

  18. A study on the development of nuclear policy to respond to international non-proliferation regimes

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Wook; Oh, K. B.; Yang, M. H.; Lee, H. M.; Ko, H. S.; Ryu, J. S.; Jung, W. H.; Lim, C. Y

    2006-01-15

    This study analyzed the trends of the nonproliferation regimes in the following three aspects. First, this study analyzed the trends of the international nuclear non-proliferation regime, which includes the NPT, the IAEA safeguards system, the international nuclear export control regime and multilateral nuclear approach. Second, this study forecast the future trends of the nonproliferation systems with the reflection of current international situations. Third, this study also analyzed outstanding issues in nuclear control regimes and derived some factors to reflect national nuclear foreign policy.

  19. Development of automatic reactor vessel inspection systems; development of data acquisition and analysis system for the nuclear vessel weld

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jong Po; Park, C. H.; Kim, H. T.; Noh, H. C.; Lee, J. M.; Kim, C. K.; Um, B. G. [Research Institute of KAITEC, Seoul (Korea)

    2002-03-01

    The objective of this project is to develop an automated ultrasonic data acquisition and data analysis system to examine heavy vessel welds. In order to examine nuclear vessel welds including reactor pressure vessel(RPV), huge amount of ultrasonic data from 6 channels should be able to be on-line processed. In addition, ultrasonic transducer scanning device should be remotely controlled, because working place is high radiation area. This kind of an automated ultrasonic testing equipment has not been developed domestically yet. In order to develop an automated ultrasonic testing system, RPV ultrasonic testing equipments developed in foreign countries were investigated and the capability of high speed ultrasonic signal processing hardwares was analyzed. In this study, ultrasonic signal processing system was designed. And also, ultrasonic data acquisition software was developed. The new systems were tested on the RPV welds of Ulchin Unit 6 to confirm their functions and capabilities. They worked very well as designed and the tests were successfully completed. 13 refs., 34 figs., 11 tabs. (Author)

  20. A Study on the Planning of Technology Development and Research for Generation IV Nuclear Energy Systems

    Energy Technology Data Exchange (ETDEWEB)

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

    2005-08-15

    This study aimed at the planning the domestic technology development of the Gen IV and the formulating the international collaborative project contents and executive plan for 'A Validity Assessment and Policies of the R and D of Generation IV Nuclear Energy Systems'. The results of the study include follows; - Survey of the technology state in the fields of the Gen IV system specific technologies and the common technologies, and the plans of the international collaborative research - Drawing up the executive research and development plan by the experts of the relevant technology field for the systems which Korean will participate in. - Formulating the effective conduction plan of the program reflecting the view of the experts from the industry, the university and the research institute. - Establishing the plan for estimation of the research fund and the manpower for the efficient utilization of the domestic available resources. This study can be useful material for evaluating the appropriateness of the Korea's participation in the international collaborative development of the Gen IV, and can be valuably utilized to establish the strategy for the effective conduction of the program. The executive plan of the research and development which was produced in this study will be used to the basic materials for the establishing the guiding direction and the strategic conduction of the program when the research and development is launched in the future.

  1. Serial nuclear transfer improves the development of interspecies reconstructed giant panda (Aluropoda melanoleuca) embryos

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    Interspecies somatic nuclear transfer (NT) may provide a new approach for preservation of the endangered rare species. Previous interspecies cloning studies have shown that a nucleus from a quiescent somatic cell supports early development of reconstructed embryos in the ooplasm from another species. In this study, we transferred nonquiescent somatic cells from a giant panda into the perivitelline space of the enucleated rabbit oocytes. After electrofusion (at the rate of 71.6%) and electrical activation, 4.2% of the panda-rabbit reconstructed embryos developed to blastocyst in vitro. For improving the development rate of reconstructed embryos, we used serial NT in this study, I.e. Blastomeres from reconstructed morulae were transferred into the perivitelline space of the enucleated rabbit oocytes. The fusion rates in the groups of serial Ⅰ, serial Ⅱ and serial Ⅲ were 79.5%, 84.1% and 78.0%, respectively, having no difference with that of somatic group. And the blastocyst rates in serial NT groups were 19.4%, 13.5% and 10.3%, respectively, which are significantly higher than that in somatic NT group. These results indicate that the nuclei from nonquiescent somatic cells can support early development of reconstructed embryos and serial NT can improve the development rate of interspecies reconstructed embryos.

  2. Development study on subcriticality monitor. 1. Report under business contract with Japan Nuclear Fuel Cycle Development Institute

    CERN Document Server

    Yamada, S

    2002-01-01

    In this trust fund, we reviewed subcriticality measuring methods and neutron or gamma ray measuring and date transmission systems appropriate for realizing inexpensive on-line criticality surveillance systems, which is required for ensuring the safety of nuclear fuel reprocessing plants. Since the neutron flux level in subcritical systems is fairly low without external neutron sources, it is desirable to use pulse type neutron detectors for subcritical measurement systems. This logically implies that subcriticality measurement methods based on the temporal domain should be used for developing an on-line criticality surveillance system. In the deep subcriticality conditions, a strong external neutron source is needed for eactivity measurement and a D-T tube can be used in order to improve the accuracy of the measurement. A D-T tube is convenient since it is free from Tritium problem since Tritium is sealed in an airtight container and also can be controlled by power supply. Hence, under deep subcritical condit...

  3. On China's Sustainable Development of Energy—Opportunity for the China's Nuclear Power Industry

    Institute of Scientific and Technical Information of China (English)

    ZengShaolun

    2005-01-01

    According to the poficy of reforming the power industry and accelerating the power construction of our country, by 2020, the national power consumption will be up to 3.6-3.7 trillion kilowatt-hours, the installed power-generating capacity is more than 800 million kilowatts. Therefore, the development of the China's nuclear power industry faces good international and domestic environments and good historical opportunities. From the point of national energy security, economic development, and resource distribution, it is analyzed that China must develop the nuclear power in a more cost-effective style in this paper.

  4. SAFT inspections for developing empirical database of fabrication flaws in nuclear reactor pressure vessels

    Science.gov (United States)

    Doctor, Steven R.; Schuster, George J.; Pardini, Allan F.

    1998-03-01

    The Pacific Northwest National Laboratory (PNNL) is developing a methodology for estimating the size and density distribution of fabrication flaws in U.S. nuclear reactor pressure vessels. This involves the nondestructive evaluation (NDE) of reactor pressure vessel materials and the destructive validation of the flaws found. NDE has been performed on reactor pressure vessel material made by Babcock & Wilcox and Combustion Engineering. A metallographic analysis is being performed to validate the flaw density and size distributions estimated from the 2500 indications of fabrication flaws that were detected and characterized in the very sensitive SAFT-UT (synthetic aperture focusing technique for ultrasonic testing) inspection data from the Pressure Vessel Research User Facility (PVRUF) vessel at Oak Ridge National Laboratory. Research plans are also described for expanding the work to include other reactor pressure vessel materials.

  5. Subsoil exploration of the estimated building site for nuclear fuel development and fabrication facility

    Energy Technology Data Exchange (ETDEWEB)

    Song, In Taek [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2000-01-01

    The objective of this report, as the result of subsoil exploration, is to provide basic design data of structural plan for nuclear fuel development and fabrication facility that is builded on Duckjin 150, Yusong, Taejeon, Korea, and provide basic data for execution of work. The soft rock level of estimated building site is deep(18.0m:BH-1, 20.5m:BH-2, 25.5m:BH-3) and the hard rock level of it is very deep (33.0m:BH-1, 46.0m:BH-2, 34.5m:BH-3) , for structural design, the hard rock shall be the bottom of foundation. 9 figs., 19 tabs. (Author)

  6. Occupational dose reduction developments and data collected at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Dionne, B.J.; Baum, J.W.

    1984-01-01

    Occupational dose reduction developments and data collected at nuclear power plants have been described. Written descriptions of repetitive high dose jobs, their collective dose equivalent ranges and list of dose reduction techniques will aid in reducing collective dose equivalents from these dose-reduction targets. Knowing which components contribute to high maintenance or repair dose will aid in reducing routine maintenance collective dose equivalents. The radwaste dose reduction improvements will aid in reducing radwaste operations collective dose equivalent and reduce the number of radwaste workers who exceed their administrative dose limits. The identification and rating of managers' and workers' ALARA incentives will provide the basis for recommendations to improve dose reduction incentives. Lastly, the identification and rating of the key components of an ALARA program will aid in

  7. Development of buffalo (Bubalus bubalis embryonic stem cell lines from somatic cell nuclear transferred blastocysts

    Directory of Open Access Journals (Sweden)

    Syed Mohmad Shah

    2015-11-01

    Full Text Available We developed buffalo embryonic stem cell lines from somatic cell nuclear transfer derived blastocysts, produced by hand-guided cloning technique. The inner cell mass of the blastocyst was cut mechanically using a Microblade and cultured onto feeder cells in buffalo embryonic stem (ES cell culture medium at 38 °C in a 5% CO2 incubator. The stem cell colonies were characterized for alkaline phosphatase activity, karyotype, pluripotency and self-renewal markers like OCT4, NANOG, SOX2, c-Myc, FOXD3, SSEA-1, SSEA-4, TRA-1-60, TRA-1-81 and CD90. The cell lines also possessed the capability to differentiate across all the three germ layers under spontaneous differentiation conditions.

  8. Low Prevalence of Chronic Beryllium Disease among Workers at a Nuclear Weapons Research and Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    Arjomandi, M; Seward, J P; Gotway, M B; Nishimura, S; Fulton, G P; Thundiyil, J; King, T E; Harber, P; Balmes, J R

    2010-01-11

    To study the prevalence of beryllium sensitization (BeS) and chronic beryllium disease (CBD) in a cohort of workers from a nuclear weapons research and development facility. We evaluated 50 workers with BeS with medical and occupational histories, physical examination, chest imaging with HRCT (N=49), and pulmonary function testing. Forty of these workers also underwent bronchoscopy for bronchoalveolar lavage (BAL) and transbronchial biopsies. The mean duration of employment at the facility was 18 yrs and the mean latency (from first possible exposure) to time of evaluation was 32 yrs. Five of the workers had CBD at the time of evaluation (based on histology or HRCT); three others had evidence of probable CBD. These workers with BeS, characterized by a long duration of potential Be exposure and a long latency, had a low prevalence of CBD.

  9. Subsoil exploration of the estimated building site for nuclear fuel development and fabrication facility

    Energy Technology Data Exchange (ETDEWEB)

    Song, In Taek [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2000-01-01

    The objective of this report, as the result of subsoil exploration, is to provide basic design data of structural plan for nuclear fuel development and fabrication facility that is builded on Duckjin 150, Yusong, Taejeon, Korea, and provide basic data for execution of work. The soft rock level of estimated building site is deep(18.0m:BH-1, 20.5m:BH-2, 25.5m:BH-3) and the hard rock level of it is very deep (33.0m:BH-1, 46.0m:BH-2, 34.5m:BH-3) , for structural design, the hard rock shall be the bottom of foundation. 9 figs., 19 tabs. (Author)

  10. Low Prevalence of Chronic Beryllium Disease Among Workers at aNuclearWeaponsResearchandDevelopmentFacility

    Science.gov (United States)

    Arjomandi, Mehrdad; Seward, James; Gotway, Michael B.; Nishimura, Stephen; Fulton, George P.; Thundiyil, Josef; King, Talmadge E.; Harber, Philip; Balmes, John R.

    2012-01-01

    Objective To study the prevalence of beryllium sensitization (BeS) and chronic beryllium disease (CBD) in a cohort of workers from a nuclear weapons research and development facility. Methods We evaluated 50 workers with BeS with medical and occupational histories, physical examination, chest imaging with high-resolution computed tomography (N = 49), and pulmonary function testing. Forty of these workers also underwent bronchoscopy for bronchoalveolar lavage and transbronchial biopsies. Results The mean duration of employment at the facility was 18 years and the mean latency (from first possible exposure) to time of evaluation was 32 years. Five of the workers had CBD at the time of evaluation (based on histology or high-resolution computed tomography); three others had evidence of probable CBD. Conclusions These workers with BeS, characterized by a long duration of potential Be exposure and a long latency, had a low prevalence of CBD. PMID:20523233

  11. Development of auxiliary shutdown panel for nuclear training center 2 simulator

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Cheul Un; Lee, Yong Kwan; Cho, Byung Hak; Park, Shin Yeol; Choi, Yong Jae; Kim, Yong Ran [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center; Kim, Sung Il; Lee, Sung Cheul; Ryuh, Kyung Shin [Korea Electric Power Corp. (KEPCO), Seoul (Korea, Republic of)

    1995-12-31

    The major object of the project is to provide emergency operating conditions to the trainees by adding simulated ASP to the existing NTC(Nuclear Training Center) 2 simulator. The other object of the project is to make KEPRI(Korea Electric Power Research Institute) be equipped with a technical know-how that is inevitable to apply its state-of-art technologies to the existing simulators in KEPCO. The contents of this report are as follows : 1. Design and manufacturing of prototype ASP. 2. Manufacturing and installation of full scope ASP. 3. Development and modification of simulator programs. 4. Integration of hardware and software, perform performance acceptance test (author). 22 refs., 9 figs.

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

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-29

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

  13. Future challenges for nuclear power plant development research, and for radiological protection sciences.

    Science.gov (United States)

    Lazo, Edward

    2007-11-01

    The promise of the future shines brightly for nuclear energy technology and production, yet also holds many challenges. Focus on new reactor designs is currently aiming at what is termed the fourth generation of reactors, which will come into operation after 2030. The 10 countries participating in the Generation-IV International Forum to develop the new generation of reactors have designated six reactor designs that will be studied. This paper will briefly discuss some of these challenges in new reactor designs in general. In addition to the challenges posed by new reactor designs, radiation protection is also faced with a series of challenges for the future. These are borne from experience with the implementation of the current system of radiological protection, from the evolution of radiation biological research, and from changes in society in the area of radiological risk assessment and management. This paper will address all of these emerging challenges, and point towards approaches to resolve them in the future.

  14. The experience in the Cernavoda Unit 1 operation - a stimulating argument for future nuclear power development in Romania

    Energy Technology Data Exchange (ETDEWEB)

    Rotaru, I. [S.N. Nuclearelectrica, S.A., Romanian Nuclear Power Company (Romania); Bucur, I. [CNE - PROD, Cernavoda Unit 1 (Romania); Galeriu, A.C. [FCN, Pitesti, Nuclear Fuel Plant (Romania); Budan, O. [S.N. Nuclearelectrica, S.A., Romanian Nuclear Power Company (Romania)

    1999-07-01

    The Romanian nuclear program has been developed based on the option for CANDU type reactors. At the beginning, this program was unrealistically conceived and its management was inappropriate. The program was reconsidered in 1990 and the management policy and organization structure were also adapted accordingly. The paper presents, in the first part, the actual organization structure, adapted for the execution of the current and future activities, related to the nuclear power program. The performance achieved by Cernavoda Unit 1 constitutes the main part of the paper. The performances described demonstrate that the Cernavoda Unit 1 is a success and the Romania's electricity needs are satisfied in a proportion of about 12% by the nuclear power. The paper also presents a general view on Cernavoda Unit 2 perspectives. The essential conclusion of the paper is that the continuation of the nuclear program appears to be a logical option, generally accepted in Romania, limited only by financial restraints. (author)

  15. Development and application of a random walk model of atmospheric diffusion in the emergency response of nuclear accidents

    Institute of Scientific and Technical Information of China (English)

    CHI Bing; LI Hong; FANG Dong

    2007-01-01

    Plume concentration prediction is one of the main contents of radioactive consequence assessment for early emergency response to nuclear accidents. Random characteristics of atmospheric diffusion itself was described, a random walk model of atmospheric diffusion (Random Walk) was introduced and compared with the Lagrangian puff model (RIMPUFF) in the nuclear emergency decision support system (RODOS) developed by the European Community for verification. The results show the concentrations calculated by the two models are quite close except that the plume area calculated by Random Walk is a little smaller than that by RIMPUFF. The random walk model for atmospheric diffusion can simulate the atmospheric diffusion in case of nuclear accidents, and provide more actual information for early emergency and consequence assessment as one of the atmospheric diffusion module of the nuclear emergency decision support system.

  16. Next Generation Nuclear Plant Reactor Pressure Vessel Materials Research and Development Plan (PLN-2803)

    Energy Technology Data Exchange (ETDEWEB)

    J. K. Wright; R. N. Wright

    2008-04-01

    The U.S. Department of Energy has selected the High Temperature Gas-cooled Reactor design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic, or pebble-bed reactor and use low-enriched uranium, Tri-Isotopic-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development Program is responsible for performing research and development on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. Studies of potential Reactor Pressure Vessel (RPV) steels have been carried out as part of the pre-conceptual design studies. These design studies generally focus on American Society of Mechanical Engineers (ASME) Code status of the steels, temperature limits, and allowable stresses. Three realistic candidate materials have been identified by this process: conventional light water reactor RPV steels A508/533, 2¼Cr-1Mo in the annealed condition, and modified 9Cr 1Mo ferritic martenistic steel. Based on superior strength and higher temperature limits, the modified 9Cr-1Mo steel has been identified by the majority of design engineers as the preferred choice for the RPV. All of the vendors have

  17. Interaction with LC8 is required for Pak1 nuclear import and is indispensable for zebrafish development.

    Directory of Open Access Journals (Sweden)

    Christine M Lightcap

    Full Text Available Pak1 (p21 activated kinase 1 is a serine/threonine kinase implicated in regulation of cell motility and survival and in malignant transformation of mammary epithelial cells. In addition, the dynein light chain, LC8, has been described to cooperate with Pak1 in malignant transformation of breast cancer cells. Pak1 itself may aid breast cancer development by phosphorylating nuclear proteins, including estrogen receptor alpha. Recently, we showed that the LC8 binding site on Pak1 is adjacent to the nuclear localization sequence (NLS required for Pak1 nuclear import. Here, we demonstrate that the LC8-Pak1 interaction is necessary for epidermal growth factor (EGF-induced nuclear import of Pak1 in MCF-7 cells, and that this event is contingent upon LC8-mediated Pak1 dimerization. In contrast, Pak2, which lacks an LC8 binding site but contains a nuclear localization sequence identical to that in Pak1, remains cytoplasmic upon EGF stimulation of MCF-7 cells. Furthermore, we show that severe developmental defects in zebrafish embryos caused by morpholino injections targeting Pak are partially rescued by co-injection of wild-type human Pak1, but not by co-injection of mutant Pak1 mRNA disrupting either the LC8 binding or the NLS site. Collectively, these results suggest that LC8 facilitates nuclear import of Pak1 and that this function is indispensable during vertebrate development.

  18. Development of an air cleaning system for dissolving high explosives from nuclear warheads

    Energy Technology Data Exchange (ETDEWEB)

    Bergman, W.; Wilson, K.; Staggs, K.; Wapman, D. [Lawrence Livermore National Lab., CA (United States)

    1997-08-01

    The Department of Energy (DOE) has a major effort underway in dismantling nuclear weapons. In support of this effort we have been developing a workstation for removing the high explosive (HE) from nuclear warheads using hot sprays of dimethyl sulfoxide (DMSO) solvent to dissolve the HE. An important component of the workstation is the air cleaning system that is used to contain DMSO aerosols and vapor and radioactive aerosols. The air cleaning system consists of a condenser to liquefy the hot DMSO vapor, a demister pad to remove most of the DMSO aerosols, a high efficiency particulate air (HEPA) filter to remove the remaining aerosols, an activated carbon filter to remove the DMSO vapor, and a final HEPA filter to meet the redundancy requirement for HEPA filters in radioactive applications. The demister pad is a 4{double_prime} thick mat of glass and steel fibers and was selected after conducting screening tests on promising candidates. We also conducted screening tests on various activated carbons and found that all had a similar performance. The carbon breakthrough curves were fitted to a modified Wheeler`s equation and gave excellent predictions for the effect of different flow rates. After all of the components were assembled, we ran a series of performance tests on the components and system to determine the particle capture efficiency as a function of size for dioctyl sebacate (DOS) and DMSO aerosols using laser particle counters and filter samples. The pad had an efficiency greater than 990% for 0.1 {mu}m DMSO particles. Test results on the prototype carbon filter showed only 70% efficiency, instead of the 99.9% in small scale laboratory tests. Thus further work will be required to develop the prototype carbon filter. 7 refs., 18 figs., 10 tabs.

  19. Development of a patient-specific dosimetry estimation system in nuclear medicine examination

    Energy Technology Data Exchange (ETDEWEB)

    Lin, H. H.; Dong, S. L.; Yang, H. J. [Dept. of Biomedical Engineering and Environmental Sciences, National Tsing-Hua Univ., Taiwan (China); Chen, S. [Dept. of Medical Imaging and Radiological Sciences, Kaohsiung Medical Univ., Taiwan (China); Shih, C. T. [Dept. of Biomedical Engineering and Environmental Sciences, National Tsing-Hua Univ., Taiwan (China); Chu