WorldWideScience

Sample records for advanced hybrid nuclear

  1. Hybrid nuclear light bulb-nuclear-pumped laser propulsion for advanced missions

    Science.gov (United States)

    Miley, G. H.

    1999-01-01

    A hybrid ``nuclear light bulb'' gaseous core reactor that can radiantly transfer energy to a propellant or alternately activate laser action is proposed for advanced space missions. The propellant mode would be employed in the phases of the mission requiring a higher thrust. However, for the bulk of the travel, the propellant would be turned off and the ultrahigh specific impulse laser mode of operation would be employed. The concept is reviewed, research and development issues are identified, and steps necessary for a feasibility demonstration are discussed.

  2. Nuclear hybrid energy infrastructure

    Energy Technology Data Exchange (ETDEWEB)

    Agarwal, Vivek; Tawfik, Magdy S.

    2015-02-01

    The nuclear hybrid energy concept is becoming a reality for the US energy infrastructure where combinations of the various potential energy sources (nuclear, wind, solar, biomass, and so on) are integrated in a hybrid energy system. This paper focuses on challenges facing a hybrid system with a Small Modular Reactor at its core. The core of the paper will discuss efforts required to develop supervisory control center that collects data, supports decision-making, and serves as an information hub for supervisory control center. Such a center will also be a model for integrating future technologies and controls. In addition, advanced operations research, thermal cycle analysis, energy conversion analysis, control engineering, and human factors engineering will be part of the supervisory control center. Nuclear hybrid energy infrastructure would allow operators to optimize the cost of energy production by providing appropriate means of integrating different energy sources. The data needs to be stored, processed, analyzed, trended, and projected at right time to right operator to integrate different energy sources.

  3. ADVANCED HYBRID PARTICULATE COLLECTOR

    Energy Technology Data Exchange (ETDEWEB)

    Stanley J. Miller; Grant L. Schelkoph; Grant E. Dunham

    2000-12-01

    A new concept in particulate control, called an advanced hybrid particulate collector (AHPC), is being developed under funding from the US Department of Energy. The AHPC combines the best features of electrostatic precipitators (ESPs) and baghouses in an entirely novel manner. The AHPC concept combines fabric filtration and electrostatic precipitation in the same housing, providing major synergism between the two methods, both in the particulate collection step and in transfer of dust to the hopper. The AHPC provides ultrahigh collection efficiency, overcoming the problem of excessive fine-particle emissions with conventional ESPs, and solves the problem of reentrainment and recollection of dust in conventional baghouses. Phase I of the development effort consisted of design, construction, and testing of a 5.7-m{sup 3}/min (200-acfm) working AHPC model. Results from both 8-hour parametric tests and 100-hour proof-of-concept tests with two different coals demonstrated excellent operability and greater than 99.99% fine-particle collection efficiency.

  4. ADVANCED HYBRID PARTICULATE COLLECTOR

    Energy Technology Data Exchange (ETDEWEB)

    Ye Zhuang; Stanley J. Miller; Michelle R. Olderbak; Rich Gebert

    2001-12-01

    A new concept in particulate control, called an advanced hybrid particulate collector (AHPC), is being developed under funding from the U.S. Department of Energy. The AHPC combines the best features of electrostatic precipitators (ESPs) and baghouses in an entirely novel manner. The AHPC concept combines fabric filtration and electrostatic precipitation in the same housing, providing major synergism between the two methods, both in the particulate collection step and in transfer of dust to the hopper. The AHPC provides ultrahigh collection efficiency, overcoming the problem of excessive fine-particle emissions with conventional ESPs, and solves the problem of reentrainment and re-collection of dust in conventional baghouses. Phase I of the development effort consisted of design, construction, and testing of a 5.7-m{sup 3}/min (200-acfm) working AHPC model. Results from both 8-hr parametric tests and 100-hr proof-of-concept tests with two different coals demonstrated excellent operability and greater than 99.99% fine-particle collection efficiency. Since all of the developmental goals of Phase I were met, the approach was scaled up in Phase II to a size of 255 m{sup 3}/min (9000 acfm) (equivalent in size to 2.5 MW) and was installed on a slipstream at the Big Stone Power Plant. For Phase II, the AHPC at Big Stone Power Plant was operated continuously from late July 1999 until mid-December 1999. The Phase II results were highly successful in that ultrahigh particle collection efficiency was achieved, pressure drop was well controlled, and system operability was excellent. For Phase III, the AHPC was modified into a more compact configuration, and components were installed that were closer to what would be used in a full-scale commercial design. The modified AHPC was operated from April to July 2000. While operational results were acceptable during this time, inspection of bags in the summer of 2000 revealed some membrane damage to the fabric that appeared to be

  5. Advanced nuclear propulsion concepts

    Energy Technology Data Exchange (ETDEWEB)

    Howe, S.D. [Los Alamos National Lab., NM (United States)

    1994-12-31

    A preliminary analysis has been carried out for two potential advanced nuclear propulsion systems: a contained pulsed nuclear propulsion engine and an antiproton initiated ICF system. The results of these studies indicate that both concepts have a high potential to help enable manned planetary exploration but require substantial development.

  6. Hybrid nuclear cycles for nuclear fission sustainability

    International Nuclear Information System (INIS)

    Nuclear fission can play and must play an important role in paving the road to Energy Sustainability. Nuclear Fission does not produce CO2 emissions, and it is already exploited at commercial level with the current NPP (Nuclear Power Plants). Most of them are based on LWR reactors, which have a very good safety record. It must be noted, however, that all LWR (including the advanced or evolutionary ones) have some drawbacks, particularly their very poor efficiency in exploiting the natural resources of nuclear fuels. In this paper, an analysis is presented on how to maximize the energy actually generated from the potential contents of fission natural resources. The role of fertile-to-fissile breeding is highlighted, as well as the need of attaining a very high safety performance in the reactors and other installations of the fuel cycle. The proposal presented in this paper is to use advanced and evolutionary LWR as energy producing reactors, and to use subcritical fast assemblies as breeders. The main result would be to increase by two orders of magnitude the percentage of energy effectively exploited from fission natural resources, while keeping a very high level of safety standards in the full fuel cycle. Breeders would not be intended for energy production, so that safety standards could rely on very low values of the thermal magnitudes, so allowing for very large safety margins for emergency cooling. Similarly, subcriticality would offer a very large margin for not to reach prompt criticality in any event. The main drawback of this proposal is that a sizeable fraction of the energy generated in the cycle (about 1/3, maybe a little more) would not be useful for the thermodynamic cycle to produce electricity. Besides that, a fraction of the generated electricity, between 5 and 10 %, would have to be recirculated to feed the accelerator activating the neutron source. Even so, the overall result would be very positive, because more than 50 % of the natural resources

  7. Performance Evaluation of the Concept of Hybrid Heat Pipe as Passive In-core Cooling Systems for Advanced Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Yeong Shin; Kim, Kyung Mo; Kim, In Guk; Bang, In Cheol [UNIST, Ulsan (Korea, Republic of)

    2015-05-15

    As an arising issue for inherent safety of nuclear power plant, the concept of hybrid heat pipe as passive in-core cooling systems was introduced. Hybrid heat pipe has unique features that it is inserted in core directly to remove decay heat from nuclear fuel without any changes of structures of existing facilities of nuclear power plant, substituting conventional control rod. Hybrid heat pipe consists of metal cladding, working fluid, wick structure, and neutron absorber. Same with working principle of the heat pipe, heat is transported by phase change of working fluid inside metal cask. Figure 1 shows the systematic design of the hybrid heat pipe cooling system. In this study, the concept of a hybrid heat pipe was introduced as a Passive IN-core Cooling Systems (PINCs) and demonstrated for internal design features of heat pipe containing neutron absorber. Using a commercial CFD code, single hybrid heat pipe model was analyzed to evaluate thermal performance in designated operating condition. Also, 1-dimensional reactor transient analysis was done by calculating temperature change of the coolant inside reactor pressure vessel using MATLAB. As a passive decay heat removal device, hybrid heat pipe was suggested with a concept of combination of heat pipe and control rod. Hybrid heat pipe has distinct feature that it can be a unique solution to cool the reactor when depressurization process is impossible so that refueling water cannot be injected into RPV by conventional ECCS. It contains neutron absorber material inside heat pipe, so it can stop the reactor and at the same time, remove decay heat in core. For evaluating the concept of hybrid heat pipe, its thermal performance was analyzed using CFD and one-dimensional transient analysis. From single hybrid heat pipe simulation, the hybrid heat pipe can transport heat from the core inside to outside about 18.20 kW, and total thermal resistance of hybrid heat pipe is 0.015 .deg. C/W. Due to unique features of long heat

  8. Performance Evaluation of the Concept of Hybrid Heat Pipe as Passive In-core Cooling Systems for Advanced Nuclear Power Plant

    International Nuclear Information System (INIS)

    As an arising issue for inherent safety of nuclear power plant, the concept of hybrid heat pipe as passive in-core cooling systems was introduced. Hybrid heat pipe has unique features that it is inserted in core directly to remove decay heat from nuclear fuel without any changes of structures of existing facilities of nuclear power plant, substituting conventional control rod. Hybrid heat pipe consists of metal cladding, working fluid, wick structure, and neutron absorber. Same with working principle of the heat pipe, heat is transported by phase change of working fluid inside metal cask. Figure 1 shows the systematic design of the hybrid heat pipe cooling system. In this study, the concept of a hybrid heat pipe was introduced as a Passive IN-core Cooling Systems (PINCs) and demonstrated for internal design features of heat pipe containing neutron absorber. Using a commercial CFD code, single hybrid heat pipe model was analyzed to evaluate thermal performance in designated operating condition. Also, 1-dimensional reactor transient analysis was done by calculating temperature change of the coolant inside reactor pressure vessel using MATLAB. As a passive decay heat removal device, hybrid heat pipe was suggested with a concept of combination of heat pipe and control rod. Hybrid heat pipe has distinct feature that it can be a unique solution to cool the reactor when depressurization process is impossible so that refueling water cannot be injected into RPV by conventional ECCS. It contains neutron absorber material inside heat pipe, so it can stop the reactor and at the same time, remove decay heat in core. For evaluating the concept of hybrid heat pipe, its thermal performance was analyzed using CFD and one-dimensional transient analysis. From single hybrid heat pipe simulation, the hybrid heat pipe can transport heat from the core inside to outside about 18.20 kW, and total thermal resistance of hybrid heat pipe is 0.015 .deg. C/W. Due to unique features of long heat

  9. Advanced Vortex Hybrid Rocket Engine (AVHRE) Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Orbital Technologies Corporation (ORBITEC) proposes to develop a unique Advanced Vortex Hybrid Rocket Engine (AVHRE) to achieve a highly-reliable, low-cost and...

  10. Advanced Vortex Hybrid Rocket Engine (AVHRE) Project

    Data.gov (United States)

    National Aeronautics and Space Administration — ORBITEC proposes to develop a unique Advanced Vortex Hybrid Rocket Engine (AVHRE) to achieve a safe, highly-reliable, low-cost and uniquely versatile propulsion...

  11. Hybrid and Electric Advanced Vehicle Systems Simulation

    Science.gov (United States)

    Beach, R. F.; Hammond, R. A.; Mcgehee, R. K.

    1985-01-01

    Predefined components connected to represent wide variety of propulsion systems. Hybrid and Electric Advanced Vehicle System (HEAVY) computer program is flexible tool for evaluating performance and cost of electric and hybrid vehicle propulsion systems. Allows designer to quickly, conveniently, and economically predict performance of proposed drive train.

  12. ADVANCED HYBRID PARTICULATE COLLECTOR; FINAL

    International Nuclear Information System (INIS)

    A new concept in particulate control, called an advanced hybrid particulate collector (AHPC), is being developed under funding from the U.S. Department of Energy. The AHPC combines the best features of electrostatic precipitators (ESPs) and baghouses in an entirely novel manner. The AHPC concept combines fabric filtration and electrostatic precipitation in the same housing, providing major synergism between the two methods, both in the particulate collection step and in transfer of dust to the hopper. The AHPC provides ultrahigh collection efficiency, overcoming the problem of excessive fine-particle emissions with conventional ESPs, and solves the problem of reentrainment and re-collection of dust in conventional baghouses. Phase I of the development effort consisted of design, construction, and testing of a 5.7-m(sup 3)/min (200-acfm) working AHPC model. Results from both 8-hr parametric tests and 100-hr proof-of-concept tests with two different coals demonstrated excellent operability and greater than 99.99% fine-particle collection efficiency. Since all of the developmental goals of Phase I were met, the approach was scaled up in Phase II to a size of 255 m(sup 3)/min (9000 acfm) (equivalent in size to 2.5 MW) and was installed on a slipstream at the Big Stone Power Plant. For Phase II, the AHPC at Big Stone Power Plant was operated continuously from late July 1999 until mid-December 1999. The Phase II results were highly successful in that ultrahigh particle collection efficiency was achieved, pressure drop was well controlled, and system operability was excellent. For Phase III, the AHPC was modified into a more compact configuration, and components were installed that were closer to what would be used in a full-scale commercial design. The modified AHPC was operated from April to July 2000. While operational results were acceptable during this time, inspection of bags in the summer of 2000 revealed some membrane damage to the fabric that appeared to be

  13. Hybrid reactors: nuclear breeding or energy production?

    OpenAIRE

    Piera, Mireia; Lafuente Mazuecos, Antonio; Abánades Velasco, Alberto; Martínez-Val Peñalosa, Jose Maria

    2010-01-01

    After reviewing the long-standing tradition on hybrid research, an assessment model is presented in order to characterize the hybrid performance under different objectives. In hybrids, neutron multiplication in the subcritical blanket plays a major role, not only for energy production and nuclear breeding, but also for tritium breeding, which is fundamental requirement in fusion–fission hybrids. All three objectives are better achieved with high values of the neutron multiplication factor (k-...

  14. Recent advances in nuclear cardiology

    DEFF Research Database (Denmark)

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

    2008-01-01

    Nuclear cardiology is an essential part of functional, non-invasive, cardiac imaging. Significant advances have been made in nuclear cardiology since planar (201)thallium ((201)TI) scintigraphy was introduced for the evaluation of left ventricular (LV) perfusion nearly 40 years ago. The use......-coronary cardiac diseases. The advances in nuclear cardiology are discussed under the four headlines of: 1) myocardial perfusion, 2) cardiac performance including LV and right ventricular (RV) function, 3) myocardial metabolism, and 4) experimental nuclear cardiology Udgivelsesdato: 2008/6...

  15. Plant sizing and evaluation of hydrogen production costs from advanced processes coupled to a nuclear heat source: Part II: Hybrid-sulphur cycle

    International Nuclear Information System (INIS)

    Hydrogen demand is already strong. It should significantly increase in the next few years due to the refinery industry's growing needs and new applications such as synthetic fuel or biofuel production. To meet the demand advanced processes are being developed throughout the world in a sustainability context. Among the most studied ones are thermochemical cycles: the sulphur-iodine and hybrid-sulphur cycles. For each of these processes, a thorough study was carried out from the flowsheet development to the final hydrogen production cost assessment, through the sizing and costing of the equipment, providing some insights about the process economic competitiveness given the current state of knowledge. This paper presents the analysis conducted for the hybrid-sulphur cycle, which leads to a hydrogen production cost around 6. 6 Euros/kg. The main contributions to that cost are discussed. (authors)

  16. Advancing against nuclear terrorism

    International Nuclear Information System (INIS)

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

  17. Recent Advances on Hybrid Intelligent Systems

    CERN Document Server

    Melin, Patricia; Kacprzyk, Janusz

    2013-01-01

    This book presents recent advances on hybrid intelligent systems using soft computing techniques for intelligent control and robotics, pattern recognition, time series prediction and optimization of complex problems. Soft Computing (SC) consists of several intelligent computing paradigms, including fuzzy logic, neural networks, and bio-inspired optimization algorithms, which can be used to produce powerful hybrid intelligent systems. The book is organized in five main parts, which contain groups of papers around a similar subject. The first part consists of papers with the main theme of hybrid intelligent systems for control and robotics, which are basically state of the art papers that propose new models and concepts, which can be the basis for achieving intelligent control and mobile robotics. The second part contains papers with the main theme of hybrid intelligent systems for pattern recognition and time series prediction, which are basically papers using nature-inspired techniques, like evolutionary algo...

  18. MERCURY CONTROL WITH ADVANCED HYBRID PARTICULATE COLLECTOR

    Energy Technology Data Exchange (ETDEWEB)

    Ye Zhuang; Stanley J. Miller

    2005-05-01

    This project was awarded under U.S. Department of Energy (DOE) National Energy Technology Laboratory (NETL) Program Solicitation DE-PS26-00NT40769 and specifically addressed Technical Topical Area 4-Testing Novel and Less Mature Control Technologies on Actual Flue Gas at the Pilot Scale. The project team included the Energy & Environmental Research Center (EERC) as the main contractor; W.L. Gore & Associates, Inc., as a technical and financial partner; and the Big Stone Power Plant operated by Otter Tail Power Company, host for the field-testing portion of the research. Since 1995, DOE has supported development of a new concept in particulate control called the advanced hybrid particulate collector (AHPC). The AHPC has been licensed to W.L. Gore & Associates, Inc., and has been marketed as the Advanced Hybrid{trademark} filter by Gore. The Advanced Hybrid{trademark} filter combines the best features of electrostatic precipitators (ESPs) and baghouses in a unique configuration, providing major synergism between the two collection methods, both in the particulate collection step and in the transfer of dust to the hopper. The Advanced Hybrid{trademark} filter provides ultrahigh collection efficiency, overcoming the problem of excessive fine-particle emissions with conventional ESPs, and it solves the problem of reentrainment and re-collection of dust in conventional baghouses. The Advanced Hybrid{trademark} filter also appears to have unique advantages for mercury control over baghouses or ESPs as an excellent gas--solid contactor. The objective of the project was to demonstrate 90% total mercury control in the Advanced Hybrid{trademark} filter at a lower cost than current mercury control estimates. The approach included bench-scale batch tests, larger-scale pilot testing with real flue gas on a coal-fired combustion system, and field demonstration at the 2.5-MW (9000-acfm) scale at a utility power plant to prove scale-up and demonstrate longer-term mercury control

  19. GE's advanced nuclear reactor designs

    International Nuclear Information System (INIS)

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

  20. Advanced teleoperation in nuclear applications

    International Nuclear Information System (INIS)

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

  1. Advanced nuclear precleaner

    International Nuclear Information System (INIS)

    This Phase II Small Business Innovation Research (SBIR) program's goal is to develop a dynamic, self-cleaning air precleaner for high-efficiency particulate air (HEPA) filtration systems that would extend significantly the life of HEPA filter banks by reducing the particulate matter that causes filter fouling and increased pack pressure. HEPA filters are widely used in DOE, Department of Defense, and a variety of commercial facilities. InnovaTech, Inc. (Formerly Micro Composite materials Corporation) has developed a proprietary dynamic separation device using a concept called Boundary Layer Momentum Transfer (BLMT) to extract particulate matter from fluid process streams. When used as a prefilter in the HVAC systems or downstream of waste vitrifiers in nuclear power plants, fuel processing facilities, and weapons decommissioning factories, the BLMT filter will dramatically extend the service life and increase the operation efficiency of existing HEPA filtration systems. The BLMT filter is self cleaning, so there will be no degraded flow or increased pressure drop. Because the BLMT filtration process is independent of temperature, it can be designed to work in ambient, medium, or high-temperature applications. During Phase II, the authors are continuing development of the computerized flow simulation model to include turbulence and incorporate expansion into a three-dimensional model that includes airflow behavior inside the filter housing before entering the active BLMT device. A full-scale (1000 ACFM) prototype filter is being designed to meet existing HEPA filter standards and will be fabricated for subsequent testing. Extensive in-house testing will be performed to determine a full range of performance characteristics. Final testing and evaluation of the prototype filter will be conducted at a DOE Quality Assurance Filter Test Station

  2. Advanced nuclear precleaner

    Energy Technology Data Exchange (ETDEWEB)

    Wright, S.R. [InnovaTech, Inc., Durham, NC (United States)

    1997-10-01

    This Phase II Small Business Innovation Research (SBIR) program`s goal is to develop a dynamic, self-cleaning air precleaner for high-efficiency particulate air (HEPA) filtration systems that would extend significantly the life of HEPA filter banks by reducing the particulate matter that causes filter fouling and increased pack pressure. HEPA filters are widely used in DOE, Department of Defense, and a variety of commercial facilities. InnovaTech, Inc. (Formerly Micro Composite materials Corporation) has developed a proprietary dynamic separation device using a concept called Boundary Layer Momentum Transfer (BLMT) to extract particulate matter from fluid process streams. When used as a prefilter in the HVAC systems or downstream of waste vitrifiers in nuclear power plants, fuel processing facilities, and weapons decommissioning factories, the BLMT filter will dramatically extend the service life and increase the operation efficiency of existing HEPA filtration systems. The BLMT filter is self cleaning, so there will be no degraded flow or increased pressure drop. Because the BLMT filtration process is independent of temperature, it can be designed to work in ambient, medium, or high-temperature applications. During Phase II, the authors are continuing development of the computerized flow simulation model to include turbulence and incorporate expansion into a three-dimensional model that includes airflow behavior inside the filter housing before entering the active BLMT device. A full-scale (1000 ACFM) prototype filter is being designed to meet existing HEPA filter standards and will be fabricated for subsequent testing. Extensive in-house testing will be performed to determine a full range of performance characteristics. Final testing and evaluation of the prototype filter will be conducted at a DOE Quality Assurance Filter Test Station.

  3. Recent Advances in Nuclear Cardiology.

    Science.gov (United States)

    Lee, Won Woo

    2016-09-01

    Nuclear cardiology is one of the major fields of nuclear medicine practice. Myocardial perfusion studies using single-photon emission computed tomography (SPECT) have played a crucial role in the management of coronary artery diseases. Positron emission tomography (PET) has also been considered an important tool for the assessment of myocardial viability and perfusion. However, the recent development of computed tomography (CT)/magnetic resonance imaging (MRI) technologies and growing concerns about the radiation exposure of patients remain serious challenges for nuclear cardiology. In response to these challenges, remarkable achievements and improvements are currently in progress in the field of myocardial perfusion imaging regarding the applicable software and hardware. Additionally, myocardial perfusion positron emission tomography (PET) is receiving increasing attention owing to its unique capability of absolute myocardial blood flow estimation. An F-18-labeled perfusion agent for PET is under clinical trial with promising interim results. The applications of F-18 fluorodeoxyglucose (FDG) and F-18 sodium fluoride (NaF) to cardiovascular diseases have revealed details on the basic pathophysiology of ischemic heart diseases. PET/MRI seems to be particularly promising for nuclear cardiology in the future. Restrictive diseases, such as cardiac sarcoidosis and amyloidosis, are effectively evaluated using a variety of nuclear imaging tools. Considering these advances, the current challenges of nuclear cardiology will become opportunities if more collaborative efforts are devoted to this exciting field of nuclear medicine. PMID:27540423

  4. Advanced nuclear systems. Review study

    International Nuclear Information System (INIS)

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

  5. Multimodal hybrid imaging agents for sentinel node mapping as a means to (re)connect nuclear medicine to advances made in robot-assisted surgery

    Energy Technology Data Exchange (ETDEWEB)

    KleinJan, Gijs H. [Leiden University Medical Hospital, Interventional Molecular Imaging Laboratory, Department of Radiology, Leiden (Netherlands); The Netherlands Cancer Institute - Antoni van Leeuwenhoek Hospital, Department of Nuclear Medicine, Amsterdam (Netherlands); Berg, Nynke S. van den [Leiden University Medical Hospital, Interventional Molecular Imaging Laboratory, Department of Radiology, Leiden (Netherlands); The Netherlands Cancer Institute - Antoni van Leeuwenhoek Hospital, Department of Urology, Amsterdam (Netherlands); Jong, Jeroen de [The Netherlands Cancer Institute - Antoni van Leeuwenhoek Hospital, Department of Pathology, Amsterdam (Netherlands); Wit, Esther M.; Poel, Henk G. van der [The Netherlands Cancer Institute - Antoni van Leeuwenhoek Hospital, Department of Urology, Amsterdam (Netherlands); Thygessen, Helene [The Netherlands Cancer Institute - Antoni van Leeuwenhoek Hospital, Department of Biostatistics, Amsterdam (Netherlands); Vegt, Erik [The Netherlands Cancer Institute - Antoni van Leeuwenhoek Hospital, Department of Nuclear Medicine, Amsterdam (Netherlands); Leeuwen, Fijs W.B. van [Leiden University Medical Hospital, Interventional Molecular Imaging Laboratory, Department of Radiology, Leiden (Netherlands); The Netherlands Cancer Institute - Antoni van Leeuwenhoek Hospital, Department of Urology, Amsterdam (Netherlands); The Netherlands Cancer Institute - Antoni van Leeuwenhoek Hospital, Department of Head and Neck Surgery and Oncology, Amsterdam (Netherlands)

    2016-07-15

    Radical prostatectomy and complementary extended pelvic lymph node dissection (ePLND) of sentinel lymph nodes (SNs) and non-sentinel lymph nodes (LNs) at risk of containing metastases are increasingly being performed using high-tech robot-assisted approaches. Although this technological evolution has clear advantages, the physical nature of robotic systems limits the integrated use of routine radioguided surgery technologies. Hence, engineering effort in robotics are focused on the integration of fluorescence guidance technologies. Using the hybrid SN tracer indocyanine green-{sup 99m}Tc-nanocolloid (radioactive and fluorescent), for the first time in combination with a robot-integrated laparoscope, we investigated whether the robot-assisted approach affects the accuracy of fluorescence detection of SNs identified preoperatively using nuclear medicine. The study included 55 patients (Briganti nomogram-based risk >5 % on LN metastases) scheduled for robot-assisted radical prostatectomy, SN biopsy and ePLND. Following indocyanine green-{sup 99m}Tc-nanocolloid injection, preoperative nuclear imaging (lymphoscintigraphy and SPECT/CT) was used to locate the SN(s). The fluorescence laparoscope was used intraoperatively to identify the SN(s) with standard fluorescence settings (in 50 patients) and with customized settings (in 5 patients). The number and location of the SNs, the radioactive, fluorescence (both in vivo and ex vivo) and tumour status of the resected SNs/LNs, and postoperative complications were recorded and analysed. Combined, preoperative lymphoscintigraphy and SPECT/CT imaging identified 212 SNs (median 4 per patient). Intraoperative fluorescence imaging using standard fluorescence settings visualized 80.4 % (148/184 SNs; 50 patients; ex vivo 97.8 %). This increased to 85.7 % (12/14 SNs; 5 patients; ex vivo 100 %) with customized fluorescence settings. SPECT/CT images provided guidance towards the residual SNs. Ex vivo all removed SNs were radioactive. SNs

  6. Multimodal hybrid imaging agents for sentinel node mapping as a means to (re)connect nuclear medicine to advances made in robot-assisted surgery

    International Nuclear Information System (INIS)

    Radical prostatectomy and complementary extended pelvic lymph node dissection (ePLND) of sentinel lymph nodes (SNs) and non-sentinel lymph nodes (LNs) at risk of containing metastases are increasingly being performed using high-tech robot-assisted approaches. Although this technological evolution has clear advantages, the physical nature of robotic systems limits the integrated use of routine radioguided surgery technologies. Hence, engineering effort in robotics are focused on the integration of fluorescence guidance technologies. Using the hybrid SN tracer indocyanine green-99mTc-nanocolloid (radioactive and fluorescent), for the first time in combination with a robot-integrated laparoscope, we investigated whether the robot-assisted approach affects the accuracy of fluorescence detection of SNs identified preoperatively using nuclear medicine. The study included 55 patients (Briganti nomogram-based risk >5 % on LN metastases) scheduled for robot-assisted radical prostatectomy, SN biopsy and ePLND. Following indocyanine green-99mTc-nanocolloid injection, preoperative nuclear imaging (lymphoscintigraphy and SPECT/CT) was used to locate the SN(s). The fluorescence laparoscope was used intraoperatively to identify the SN(s) with standard fluorescence settings (in 50 patients) and with customized settings (in 5 patients). The number and location of the SNs, the radioactive, fluorescence (both in vivo and ex vivo) and tumour status of the resected SNs/LNs, and postoperative complications were recorded and analysed. Combined, preoperative lymphoscintigraphy and SPECT/CT imaging identified 212 SNs (median 4 per patient). Intraoperative fluorescence imaging using standard fluorescence settings visualized 80.4 % (148/184 SNs; 50 patients; ex vivo 97.8 %). This increased to 85.7 % (12/14 SNs; 5 patients; ex vivo 100 %) with customized fluorescence settings. SPECT/CT images provided guidance towards the residual SNs. Ex vivo all removed SNs were radioactive. SNs were tumour

  7. Advances in the study of hybrid finite elements

    Institute of Scientific and Technical Information of China (English)

    2000-01-01

    Some new concepts and research progress in hybrid finite elements advanced in recent years are in troduced. On the basis of incompatible energy consistency analysis, the optimal condition of hybrid elements is derived and the formulation for fulfilling this condition is given. A post-processing penalty equilibrium optimization technique of hybrid element is presented to create high quality hybrid model. For incompressible problems, a method of deviatoric hybrid element is proposed and unification of computation between compressible and incompressible media is achieved.

  8. Advanced nuclear systems in comparison

    International Nuclear Information System (INIS)

    This study aims at a comparison of future reactor concepts, paying particular attention to aspects of safety, of the fuel cycle, the economics, the experience-base and the state of development. Representative examples of typical development lines, that could possibly be 'of interest' within a time horizon of 50 years were selected for comparison. This can be divided into three phases: - Phase I includes the next 10 years and will be characterised mainly by evolutionary developments of light water reactors (LWR) of large size; representative: EPR, - Phase II: i.e. the time between 2005 and 2020 approximately, encompasses the forecasted doubling of today's world-wide installed nuclear capacity; along with evolutionary reactors, innovative systems like AP600, PIUS, MHTGR, EFR will emerge, - Phase III covers the time between 2020 and 2050 and is characterised by the issue of sufficient fissile material resources; novel fast reactor systems including hybrid systems can, thus, become available; representatives: IFR, EA, ITER (the latter being). The evaluated concepts foresee partly different fuel cycles. Fission reactors can be operated in principle on the basis of either a Uranium-Plutonium-cycle or a Thorium-Uranium-cycle, while combinations of these cycles among them or with other reactor concepts than proposed are possible. With today's nuclear park (comprising mainly LWRs), the world-wide plutonium excess increases annually by about 100 t. Besides strategies based on reprocessing like: - recycling in thermal and fast reactors with mixed oxide fuels, - plutonium 'burning' in reactors with novel fuels without uranium or in 'hybrid' systems, allowing a reduction of this excess, direct disposal of spent fuel elements including their plutonium content ('one-through') is being considered. (author) figs., tabs., 32 refs

  9. Advances in Nuclear Monitoring Technologies

    Science.gov (United States)

    Park, Brent

    2006-03-01

    Homeland security requires low-cost, large-area detectors for locating and identifying weapons-usable nuclear materials and monitors for radiological isotopes that are more robust than current systems. Recent advances in electronics materials and nanotechnology, specifically organic semiconductors and inorganic quantum dots, offer potential improvements. We provide an overview of the physical processes involved in radiation detection using these new materials in the design of new device structures. Examples include recent efforts on quantum dots, as well as more traditional radiation-detecting materials such as CdZnTe and high-pressure xenon. Detector improvements demand not only new materials but also enhanced data-analysis tools that reduce false alarms and thus increase the quality of decisions. Additional computing power on hand-held platforms should enable the application of advanced algorithms to radiation-detection problems in the field, reducing the need to transmit data and thus delay analysis.

  10. Advanced hybrid vehicle propulsion system study

    Science.gov (United States)

    Schwarz, R.

    1982-01-01

    Results are presented of a study of an advanced heat engine/electric automotive hybrid propulsion system. The system uses a rotary stratified charge engine and ac motor/controller in a parallel hybrid configuration. The three tasks of the study were (1) parametric studies involving five different vehicle types, (2) design trade-off studies to determine the influence of various vehicle and propulsion system paramaters on system performance fuel economy and cost, and (3) a conceptual design establishing feasibility at the selected approach. Energy consumption for the selected system was .034 1/km (61.3 mpg) for the heat engine and .221 kWh/km (.356 kWh/mi) for the electric power system over a modified J227 a schedule D driving cycle. Life cycle costs were 7.13 cents/km (11.5 cents/mi) at $2/gal gasoline and 7 cents/kWh electricity for 160,000 km (100,000 mi) life.

  11. Recent Advances in Nuclear Medicine Imaging Instrumentation

    International Nuclear Information System (INIS)

    This review introduces advances in clinical and pre-clinical single photon emission computed tomography (SPECT) and positron emission tomography (PET) providing noninvasive functional images of biological processes. Development of new collimation techniques such as multi-pinhole and slit-slat collimators permits the improvement of system spatial resolution and sensitivity of SPECT. Application specific SPECT systems using smaller and compact solid-state detector have been customized for myocardial perfusion imaging with higher performance. Combined SPECT/CT providing improved diagnostic and functional capabilities has been introduced. Advances in PET and CT instrumentation have been incorporated in the PET/CT design that provide the metabolic information from PET superimposed on the anatomic information from CT. Improvements in the sensitivity of PET have achieved by the fully 3D acquisition with no septa and the extension of axial field-of-view. With the development of faster scintillation crystals and electronics, time-of-flight (TOF) PET is now commercially available allowing the increase in the signal-to-noise ratio by incorporation of TOF information into the PET reconstruction process. Hybrid PET/SPECT/CT systems has become commercially available for molecular imaging in small animal models. The pre-clinical systems have improved spatial resolution using depth-of-interaction measurement and new collimators. The recent works on solid state detector and dual modality nuclear medicine instrumentations incorporating MRI and optical images will also be discussed

  12. ADVANCED HYBRID PARTICULATE COLLECTOR - PHASE III

    International Nuclear Information System (INIS)

    A new concept in particulate control, called an advanced hybrid particulate collector (AHPC), is being developed under funding from the U.S. Department of Energy. The AHPC combines the best features of electrostatic precipitators (ESPs) and baghouses in a unique configuration. The AHPC concept consists of a combination of fabric filtration and electrostatic precipitation in the same housing, providing major synergism between the two collection methods, both in the particulate collection step and in the transfer of dust to the hopper. The AHPC provides ultrahigh collection efficiency, overcoming the problem of excessive fine-particle emission with conventional ESPs, and it solves the problem of reentrainment and re-collection of dust in conventional baghouses. In Phase II, a 2.5-MW-scale AHPC was designed, constructed, installed, and tested at the Big Stone power plant. For Phase III, further testing of an improved version of the 2.5-MW-scale AHPC at the Big Stone power plant is being conducted to facilitate commercialization of the AHPC technology

  13. Justification of the hybrid nuclear medicine examinations

    International Nuclear Information System (INIS)

    The annual frequency of nuclear medicine examinations is increasing worldwide. This is partly a consequence of the recently introduced single photon emission tomography, combined with computed tomography, and positron emission tomography, combined with computed tomography, techniques, which combine functional, metabolic and morphological information important for the diagnosis of many diseases. However, since the effective radiation dose is the sum of the dose of two components, the hybrid examinations result in increased patient exposure. Accordingly, their justification becomes mandatory. It starts with their clinical importance-the opportunity to resolve a clinical problem decisive for patients' management. Knowledge of the indications, contraindications and the examinations' limitations is the responsibility of the nuclear medicine physician, as well as the choice of the most adequate examination and protocol. In conclusion, the cost and the accessibility of the examinations should not be the principal consideration as opposed to the diagnostic value and the exposure. Flexible protocols and algorithms should be used for hybrid nuclear medicine examinations. (authors)

  14. Advanced Coal Wind Hybrid: Economic Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Phadke, Amol; Goldman, Charles; Larson, Doug; Carr, Tom; Rath, Larry; Balash, Peter; Yih-Huei, Wan

    2008-11-28

    Growing concern over climate change is prompting new thinking about the technologies used to generate electricity. In the future, it is possible that new government policies on greenhouse gas emissions may favor electric generation technology options that release zero or low levels of carbon emissions. The Western U.S. has abundant wind and coal resources. In a world with carbon constraints, the future of coal for new electrical generation is likely to depend on the development and successful application of new clean coal technologies with near zero carbon emissions. This scoping study explores the economic and technical feasibility of combining wind farms with advanced coal generation facilities and operating them as a single generation complex in the Western US. The key questions examined are whether an advanced coal-wind hybrid (ACWH) facility provides sufficient advantages through improvements to the utilization of transmission lines and the capability to firm up variable wind generation for delivery to load centers to compete effectively with other supply-side alternatives in terms of project economics and emissions footprint. The study was conducted by an Analysis Team that consists of staff from the Lawrence Berkeley National Laboratory (LBNL), National Energy Technology Laboratory (NETL), National Renewable Energy Laboratory (NREL), and Western Interstate Energy Board (WIEB). We conducted a screening level analysis of the economic competitiveness and technical feasibility of ACWH generation options located in Wyoming that would supply electricity to load centers in California, Arizona or Nevada. Figure ES-1 is a simple stylized representation of the configuration of the ACWH options. The ACWH consists of a 3,000 MW coal gasification combined cycle power plant equipped with carbon capture and sequestration (G+CC+CCS plant), a fuel production or syngas storage facility, and a 1,500 MW wind plant. The ACWH project is connected to load centers by a 3,000 MW

  15. Advanced Hybrid Particulate Collector Project Management Plan

    Energy Technology Data Exchange (ETDEWEB)

    Miller, S.J.

    1995-11-01

    As the consumption of energy increases, its impact on ambient air quality has become a significant concern. Recent studies indicate that fine particles from coal combustion cause health problems as well as atmospheric visibility impairment. These problems are further compounded by the concentration of hazardous trace elements such as mercury, cadmium, selenium, and arsenic in fine particles. Therefore, a current need exists to develop superior, but economical, methods to control emissions of fine particles. Since most of the toxic metals present in coal will be in particulate form, a high level of fine- particle collection appears to be the best method of overall air toxics control. However, over 50% of mercury and a portion of selenium emissions are in vapor form and cannot be collected in particulate control devices. Therefore, this project will focus on developing technology not only to provide ultrahigh collection efficiency of particulate air toxic emissions, but also to capture vapor- phase trace metals such as mercury and selenium. Currently, the primary state-of-the-art technologies for particulate control are fabric filters (baghouses) and electrostatic precipitators (ESPs). However, they both have limitations that prevent them from achieving ultrahigh collection of fine particulate matter and vapor-phase trace metals. The objective of this project is to develop a highly reliable advanced hybrid particulate collector (AHPC) that can provide > 99.99 % particulate collection efficiency for all particle sizes between 0.01 and 50 14m, is applicable for use with all U.S. coals, and is cost-0443competitive with existing technologies. Phase I of the project is organized into three tasks: Task I - Project Management, Reporting, and Subcontract Consulting Task 2 - Modeling, Design, and Construction of 200-acfm AHPC Model Task 3 - Experimental Testing and Subcontract Consulting

  16. Nuclear Hybrid Energy Systems: Challenges and Opportunities

    Energy Technology Data Exchange (ETDEWEB)

    P. Sabharwall; S.B. Sitton; S.J. Yoon; C. Stoots

    2014-07-01

    With growing demand of energy and costs of the fossil fuels, coupled with the environmental concerns have resulted in an increased interest in alternative energy sources. Nuclear hybrid energy systems (NHES) are being considered which incorporates renewable energy sources such as solar and wind energy combined with nuclear reactor and energy storage to meet the peak hours demand imposed on the grid, along with providing process heat for other potential industrial applications. This concept could potentially satisfy various energy demands and improve reliability, robustness and resilience for the entire system as a whole, along with economic and net efficiency gains. This paper provides a brief understanding of potential NHES system and architecture along with the challenges

  17. Advanced propulsion system concept for hybrid vehicles

    Science.gov (United States)

    Bhate, S.; Chen, H.; Dochat, G.

    1980-01-01

    A series hybrid system, utilizing a free piston Stirling engine with a linear alternator, and a parallel hybrid system, incorporating a kinematic Stirling engine, are analyzed for various specified reference missions/vehicles ranging from a small two passenger commuter vehicle to a van. Parametric studies for each configuration, detail tradeoff studies to determine engine, battery and system definition, short term energy storage evaluation, and detail life cycle cost studies were performed. Results indicate that the selection of a parallel Stirling engine/electric, hybrid propulsion system can significantly reduce petroleum consumption by 70 percent over present conventional vehicles.

  18. A hybrid charge sensitive preamplifier for nuclear spectroscopy applications

    International Nuclear Information System (INIS)

    An indigenous hybrid based preamplifier has been designed and developed successfully in collaboration with BEL, Bangalore. These hybrids are commercially available from BEL, Bangalore with part name as BMC 1521. The hybrids provide flexibility of selecting input JFET, feedback resistor and feedback capacitor, thus making it useful for a wide range of nuclear spectroscopy applications. (author)

  19. Nuclear Thermal Propulsion for Advanced Space Exploration

    Science.gov (United States)

    Houts, M. G.; Borowski, S. K.; George, J. A.; Kim, T.; Emrich, W. J.; Hickman, R. R.; Broadway, J. W.; Gerrish, H. P.; Adams, R. B.

    2012-01-01

    The fundamental capability of Nuclear Thermal Propulsion (NTP) is game changing for space exploration. A first generation Nuclear Cryogenic Propulsion Stage (NCPS) based on NTP could provide high thrust at a specific impulse above 900 s, roughly double that of state of the art chemical engines. Characteristics of fission and NTP indicate that useful first generation systems will provide a foundation for future systems with extremely high performance. The role of the NCPS in the development of advanced nuclear propulsion systems could be analogous to the role of the DC-3 in the development of advanced aviation. Progress made under the NCPS project could help enable both advanced NTP and advanced Nuclear Electric Propulsion (NEP).

  20. Nuclear propulsion technology advanced fuels technology

    Science.gov (United States)

    Stark, Walter A., Jr.

    1993-01-01

    Viewgraphs on advanced fuels technology are presented. Topics covered include: nuclear thermal propulsion reactor and fuel requirements; propulsion efficiency and temperature; uranium fuel compounds; melting point experiments; fabrication techniques; and sintered microspheres.

  1. Advances in nuclear science and technology

    CERN Document Server

    Henley, Ernest J

    1962-01-01

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

  2. Recent advances in nuclear ADC's

    International Nuclear Information System (INIS)

    Electronics Division of BARC has done leading research work in nuclear ADC's. Number of new methods have been developed. The most important of these methods are: (1) the vernier Approximation Technique, (2) the method based on new DAC correction technique, and (3) the Interpolation Technique. These are briefly described. High resolution (8K and 4K) nuclear ADC's constructed based on new methods of A/D conversion give low DNL ( < ± 1 per cent) and low conversion time (< 10 μsec). These ADC's give much lower conversion time as compared to the conversion time obtained using Wilkinson technique. Thus 100 MHz Wilkinson type of ADC with 8K resolution has conversion time of 81 micro seconds which is very high as compared to conversion time of 6.5 micro secs. of the 8K nuclear ADC made at Electronics Division, BARC. All these nuclear ADC's utilize commercially available monolithic ADC's and monolithic DAC's. The recent improvements in speed size and cost of these ADC's and DAC's are thus directly utilized to improve corresponding factors in nuclear ADC's. Thus conversion time of 4K nuclear ADC can be reduced from 12 μsec to nearly 4 μsec just with replacement of ADC-84 by its high speed version. This is a distinct advantage of these nuclear ADC's over Wilkinson type of ADC's, where improvement of performance requires major changes in circuit design. (author). 5 refs., 3 figs

  3. Lower Hybrid antennas for nuclear fusion experiments

    CERN Document Server

    Hillairet, Julien; Bae, Young-Soon; Bai, X; Balorin, C; Baranov, Y; Basiuk, V; Bécoulet, A; Belo, J; Berger-By, G; Brémond, S; Castaldo, C; Ceccuzzi, S; Cesario, R; Corbel, E; Courtois, X; Decker, J; Delmas, E; Delpech, L; Ding, X; Douai, D; Ekedahl, A; Goletto, C; Goniche, M; Guilhem, D; Hertout, P; Imbeaux, F; Litaudon, X; Magne, R; Mailloux, J; Mazon, D; Mirizzi, F; Mollard, P; Moreau, P; Oosako, T; Petrzilka, V; Peysson, Y; Poli, S; Preynas, M; Prou, M; Saint-Laurent, F; Samaille, F; Saoutic, B

    2015-01-01

    The nuclear fusion research goal is to demonstrate the feasibility of fusion power for peaceful purposes. In order to achieve the conditions similar to those expected in an electricity-generating fusion power plant, plasmas with a temperature of several hundreds of millions of degrees must be generated and sustained for long periods. For this purpose, RF antennas delivering multi-megawatts of power to magnetized confined plasma are commonly used in experimental tokamaks. In the gigahertz range of frequencies, high power phased arrays known as "Lower Hybrid" (LH) antennas are used to extend the plasma duration. This paper reviews some of the technological aspects of the LH antennas used in the Tore Supra tokamak and presents the current design of a proposed 20 MW LH system for the international experiment ITER.

  4. Advances in nuclear science and technology

    CERN Document Server

    Henley, Ernest J

    1970-01-01

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

  5. Advances in nuclear science and technology

    CERN Document Server

    Greebler, Paul

    1966-01-01

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

  6. Robot vision for nuclear advanced robot

    International Nuclear Information System (INIS)

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

  7. Impact of fusion-fission hybrids on world nuclear future

    International Nuclear Information System (INIS)

    An investigation has been conducted to examine the impact of fusion-fission hybrids on world nuclear future. The primary objectives of this investigation have been: (1) to determine whether hybrids can allow us to meet the projected nuclear component of the world energy demand within current estimates of uranium resources without fast breeders, and (2) to identify the preferred hybrid concept from a resource standpoint. The results indicate that hybrids have the potential to lower the world uranium demand to values well below the resource base. However, the time window for hybrid introduction is quite near and narrow (2000-2020). If historical market penetration rates are assumed, the demand will not be met within the resource base unless hybrids are coupled to the breeders. The results also indicate that from a resource standpoint hybrids which breed their own tritium and have a low blanket energy multiplication are preferable. (orig.)

  8. Advances in nuclear science and technology

    CERN Document Server

    Henley, Ernest J

    1972-01-01

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

  9. Advances in nuclear science and technology

    CERN Document Server

    Henley, Ernest J

    1976-01-01

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

  10. Advanced propulsion system for hybrid vehicles

    Science.gov (United States)

    Norrup, L. V.; Lintz, A. T.

    1980-01-01

    A number of hybrid propulsion systems were evaluated for application in several different vehicle sizes. A conceptual design was prepared for the most promising configuration. Various system configurations were parametrically evaluated and compared, design tradeoffs performed, and a conceptual design produced. Fifteen vehicle/propulsion systems concepts were parametrically evaluated to select two systems and one vehicle for detailed design tradeoff studies. A single hybrid propulsion system concept and vehicle (five passenger family sedan)were selected for optimization based on the results of the tradeoff studies. The final propulsion system consists of a 65 kW spark-ignition heat engine, a mechanical continuously variable traction transmission, a 20 kW permanent magnet axial-gap traction motor, a variable frequency inverter, a 386 kg lead-acid improved state-of-the-art battery, and a transaxle. The system was configured with a parallel power path between the heat engine and battery. It has two automatic operational modes: electric mode and heat engine mode. Power is always shared between the heat engine and battery during acceleration periods. In both modes, regenerative braking energy is absorbed by the battery.

  11. Advanced nuclear power plants in Korea

    International Nuclear Information System (INIS)

    Full text: Korea Hydro and Nuclear Power Co., Ltd (KHNP) is the largest power company among the six subsidiaries that separated from Korea Electric Power Corporation (KEPCO) in 2001, accounting for approximately 25% of electricity producing facilities, hydro and nuclear combined. KHNP operates 20 nuclear power plants in Kori, Yonggwang, Ulchin and Wolsong site and several hydroelectric power generation facilities, providing approximately 36% of the national power supply. As a major source of electricity generation in Korea, nuclear energy contributes greatly to the stability of national electricity supply and energy security. KHNP's commercial nuclear power plant operation, which started with Kori Unit 1 in 1978, has achieved an average capacity factor more than 90% since 2000 and a high record of 93.4% in 2008. Following the introduction of nuclear power plants in the 1970's, Korea accumulated its nuclear technology in the 1980's, developed OPR 1000(Optimized Power Reactor) and demonstrated advanced level of its nuclear technology capabilities in the 2000's by developing an advanced type reactor, APR 1400(Advanced Power Reactor) which is being constructed at Shin-Kori Unit 3 and 4 for the first time. By 2022, KHNP will construct additional 12 nuclear power plants in order to ensure a stable power supply according to the Government Plan of Long-Term Electricity supply and Demand. 4 units of OPR 1000 reactor model will be commissioned by 2013 and 8 units of APR 1400 are under construction and planned. At the end of 2022, the nuclear capacity will reach 33% share of total generation capacity in Korea and account for 48% of national power generation. (author)

  12. Advanced nuclear reactor systems - an Indian perspective

    International Nuclear Information System (INIS)

    The Indian nuclear power programme envisages use of closed nuclear fuel cycle and thorium utilisation as its mainstay for its sustainable growth. The current levels of deployment of nuclear energy in India need to be multiplied nearly hundred fold to reach levels of electricity generation that would facilitate the country to achieve energy independence as well as a developed status. The Indian thorium based nuclear energy systems are being developed to achieve sustainability in respect of fuel resource along with enhanced safety and reduced waste generation. Advanced Heavy Water Reactor and its variants have been designed to meet these objectives. The Indian High Temperature Reactor programme also envisages use of thorium-based fuel with advanced levels of passive safety features. (author)

  13. Coordinating Space Nuclear Research Advancement and Education

    International Nuclear Information System (INIS)

    The advancement of space exploration using nuclear science and technology has been a goal sought by many individuals over the years. The quest to enable space nuclear applications has experienced many challenges such as funding restrictions; lack of political, corporate, or public support; and limitations in educational opportunities. The Center for Space Nuclear Research (CSNR) was established at the Idaho National Laboratory (INL) with the mission to address the numerous challenges and opportunities relevant to the promotion of space nuclear research and education.1 The CSNR is operated by the Universities Space Research Association and its activities are overseen by a Science Council comprised of various representatives from academic and professional entities with space nuclear experience. Program participants in the CSNR include academic researchers and students, government representatives, and representatives from industrial and corporate entities. Space nuclear educational opportunities have traditionally been limited to various sponsored research projects through government agencies or industrial partners, and dedicated research centers. Centralized research opportunities are vital to the growth and development of space nuclear advancement. Coordinated and focused research plays a key role in developing the future leaders in the space nuclear field. The CSNR strives to synchronize research efforts and provide means to train and educate students with skills to help them excel as leaders.

  14. IMPULSE - advanced nuclear thermal propulsion

    Energy Technology Data Exchange (ETDEWEB)

    Ivanenok, J.F. III; Wett, J.F. [Westinghouse Electric Corp., Pittsburgh, PA (United States)

    1993-12-31

    The IMPULSE nuclear thermal rocket concept provides an evolutionary step toward high thrust-to-weight and specific impulse over a wide operating range. Most of the components and features of the concept are based on demonstrated or proven technology from the NER VA/Rover program. The performance increase is due to the use of a new solid nuclear fuel shape. The new fuel shape provides a large flow area while maintaining flow control and eliminating hot spots due to fuel-to-fuel contact. The control and eliminating hot spots due to fuel-to-fuel contact. The IMPULSE reactor utilizes a multi-pass, series flow configuration to provide excess turbine power while improving the thermal efficiency of the overall system. This configuration also provides a large area for moderator. The IMPULSE concept can provide a specific impulse of up to 1000 seconds and trust to weight ratios approaching 40. The improved performance will reduce the Initial Mass In Low Earth Orbit (IMLEO) and provide a consequent reduction in launch costs and logistics problems.

  15. Advances in nuclear desalination in BARC

    International Nuclear Information System (INIS)

    As a part of our programme to improve the quality of life of our large population by systematic induction of nuclear energy, BARC has been engaged in R and D activities on desalination since 1970s. The desalination activities were part of a programme of setting up a number of demonstration plants for the energy intensive processes such as desalination of seawater, electrolytic production of hydrogen and electro thermal production of phosphorus. These activities are presently termed by IAEA as 'Non Electrical Application of Nuclear Energy'. Over a period of time, BARC has successfully developed desalination technologies based on multi-stage flash (MSF) evaporation, reverse osmosis (RO) and low temperature evaporation (LTE). In the field of thermal desalination, efforts are directed towards utilizing the low-grade heat and the waste heat as energy input for desalination. In membrane desalination, work is being carried out on newer pre-treatment methods such as use of ultra filtration, energy reduction and higher membrane life. Based on operational experience of MSF and RO plants at Trombay, BARC has undertaken establishment of the Nuclear Desalination Demonstration Project (NDDP), Kalpakkam. NDDP consists of a hybrid MSF-RO desalination plant of 6300 m3/d capacity (4500 m3/d MSF and 1800 m3/d Sea Water Reverse Osmosis (SWRO)) coupled to 2 x 170 MWe Pressurised Heavy Water Reactors (PHWRs) at MAPS, Kalpakkam. The requirements of seawater, steam and electrical power for the desalination plants are met from MAPS I and II which are around 1.5%, 1.0% and 0.5% of available at MAPS. The hybrid plant has provision for redundancy, utilization of streams from one to other and production of two qualities of products for their best utilization. The 1800 m3/d SWRO plant, which is already commissioned in August 2002, is designed to operate at relatively lower pressure (51.5 bar during 1st year and 54 bar during 3rd year) to save energy, employs lesser pre-treatment (because of

  16. Advances in nuclear science and technology

    CERN Document Server

    Henley, Ernest J

    1973-01-01

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

  17. Advances in nuclear science and technology

    CERN Document Server

    Greebler, Paul

    1968-01-01

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

  18. Nuclear Hybrid Energy Systems: Imperatives, Prospects, and Challenges

    International Nuclear Information System (INIS)

    As global population reaches an expected 8 billion people by 2030, primary energy consumption is expected to increase by almost 40% from approximately 520 exajoules consumed today to almost 740 exajoules. Much of this increase is expected to come from non-Organization for Economic Cooperation and Development (OECD) nations, and Asia specifically. In these economies, energy used for transportation is expected to grow substantially, as is industrial, commercial and to a lesser degree residential energy use, creating considerable pressure on global and local energy markets. The magnitude and timing of growth in energy consumption likely will create a global imperative to deploy energy production technologies that balance the three pillars of energy security: (1) economic stability - related to the affordability of energy products, stability and predictability in their price, and the efficient and effective deployment of global capital resources in their development; (2) environmental sustainability - related to minimizing the negative impacts of energy production to air, land, and water systems and advancing the long-term viability of using a particular resource in a way that does not limit future generations ability to prosper; (3) resource security - related to the ability to access energy resources and products where and when necessary, in an affordable and predictable manner. One approach to meeting these objectives is hybrid energy systems (HES). Broadly described, HES are energy product production plants that take two or more energy resource inputs (typically includes both carbon and non-carbon based sources) and produce two or more energy products (e.g. electricity, liquid transportation fuels, industrial chemicals) in an integrated plant. Nuclear energy integration into HES offers intriguing potential, particularly if smaller (<300 MWe) reactors are available. Although the concept of using nuclear energy in a variety of non-electrical process applications is

  19. Nuclear Hybrid Energy Systems: Imperatives, Prospects, and Challenges

    Energy Technology Data Exchange (ETDEWEB)

    Steven E. Aumeier

    2010-10-01

    As global population reaches an expected 8 billion people by 2030, primary energy consumption is expected to increase by almost 40% from approximately 520 exajoules consumed today to almost 740 exajoules. Much of this increase is expected to come from non-Organization for Economic Cooperation and Development (OECD) nations, and Asia specifically. In these economies, energy used for transportation is expected to grow substantially, as is industrial, commercial and to a lesser degree residential energy use, creating considerable pressure on global and local energy markets. The magnitude and timing of growth in energy consumption likely will create a global imperative to deploy energy production technologies that balance the three pillars of energy security: • economic stability – related to the affordability of energy products, stability and predictability in their price, and the efficient and effective deployment of global capital resources in their development; • environmental sustainability – related to minimizing the negative impacts of energy production to air, land, and water systems and advancing the long-term viability of using a particular resource in a way that does not limit future generations ability to prosper; • resource security – related to the ability to access energy resources and products where and when necessary, in an affordable and predictable manner. One approach to meeting these objectives is hybrid energy systems (HES). Broadly described, HES are energy product production plants that take two or more energy resource inputs (typically includes both carbon and non-carbon based sources) and produce two or more energy products (e.g. electricity, liquid transportation fuels, industrial chemicals) in an integrated plant. Nuclear energy integration into HES offers intriguing potential, particularly if smaller (<300 MWe) reactors are available. Although the concept of using nuclear energy in a variety of non-electrical process

  20. Advanced Geometric Modeler with Hybrid Representation

    Institute of Scientific and Technical Information of China (English)

    杨长贵; 陈玉健; 等

    1996-01-01

    An advanced geometric modeler GEMS4.0 has been developed,in which feature representation is used at the highest level abstraction of a product model.Boundary representation is used at the bottom level,while CSG model is adopted at the median level.A BRep data structure capable of modeling non-manifold is adopted.UNRBS representation is used for all curved surfaces,Quadric surfaces have dual representations consisting of their geometric data such as radius,center point,and center axis.Boundary representation of free form surfaces is easily built by sweeping and skinning method with NURBS geometry.Set operations on curved solids with boundary representation are performed by an evaluation process consisting of four steps.A file exchange facility is provided for the conversion between product data described by STEP and product information generated by GEMS4.0.

  1. Advanced control design for hybrid turboelectric vehicle

    Science.gov (United States)

    Abban, Joseph; Norvell, Johnesta; Momoh, James A.

    1995-08-01

    The new environment standards are a challenge and opportunity for industry and government who manufacture and operate urban mass transient vehicles. A research investigation to provide control scheme for efficient power management of the vehicle is in progress. Different design requirements using functional analysis and trade studies of alternate power sources and controls have been performed. The design issues include portability, weight and emission/fuel efficiency of induction motor, permanent magnet and battery. A strategic design scheme to manage power requirements using advanced control systems is presented. It exploits fuzzy logic, technology and rule based decision support scheme. The benefits of our study will enhance the economic and technical feasibility of technological needs to provide low emission/fuel efficient urban mass transit bus. The design team includes undergraduate researchers in our department. Sample results using NASA HTEV simulation tool are presented.

  2. Advanced research workshop: nuclear materials safety

    Energy Technology Data Exchange (ETDEWEB)

    Jardine, L J; Moshkov, M M

    1999-01-28

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

  3. The Advanced BWR Nuclear Plant: Safe, economic nuclear energy

    Energy Technology Data Exchange (ETDEWEB)

    Redding, J.R. [GE Nuclear Energy, San Jose, CA (United States)

    1994-12-31

    The safety and economics of Advanced BWR Nuclear Power Plants are outlined. The topics discussed include: ABWR Programs: status in US and Japan; ABWR competitiveness: safety and economics; SBWR status; combining ABWR and SBWR: the passive ABWR; and Korean/GE partnership.

  4. Advanced components for electric and hybrid electric vehicles. Workshop proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Stricklett, K.L.; Cookson, A.H.; Bartholomew, R.W.; Leedy, T. [National inst. of Standards and Technology, Gaithersburg, MD (United States). Electricity Div.

    1994-12-31

    This is a key period in the development of electric and hybrid electric vehicles. The landmark 1990 legislation in California requires that 2 percent of new automobiles be zero emission vehicles in 1998, rising to 10 percent in the year 2005. This can only be met by electric vehicles. The purpose of the workshop was to concentrate on the technologies to improve the design, performance, manufacturability, and economics of the critical components for the next generation of electric and hybrid electric vehicles for the year 2000 and beyond. The workshop began with invited speakers to cover the general topics of impact of the California legislation, Federal agency programs, development of standards, infrastructure needs, advanced battery development, and the imperatives for commercial success of electric and hybrid electric vehicles. Working sessions were five parallel meetings on Energy Conversion Systems, Energy Storage Systems, Electric Propulsion Systems, Controls and Instrumentation, and Ancillary Systems.

  5. Communicating about advanced nuclear energy plants

    International Nuclear Information System (INIS)

    The success of advanced nuclear energy plants, as with any new product, will not depend on design alone. Success will require public support and good communications to achieve that support. In the past, communication weaknesses - including mixed and confusing messages - have sometimes created barriers between the technical community and the public. Several lessons learned from a decade of social science research in the United States of America have implications for communicating effectively about advanced design nuclear energy plants: (1) Most audiences are open-minded and receptive to communications on this topic. They view nuclear energy as a fuel of the future and want to be comfortable about the future. Most people in the USA (82%) expect future nuclear energy plants to be safer, so the improvements being made are simply consistent with public expectations. (2) Few people pay close attention to energy issues. (3) Communications must be simple and free of jargon. Because people do not pay close attention to the issues, their knowledge is limited. Some terms used by the industry to describe advanced design plants are misinterpreted. (4) Good communications focus on consumer wants and values, not industry needs or problems. People care about generational responsibility, planning for the future, environmental protection and security. (5) Benefits and safeguards should be shown instead of risk comparisons. Generic benefits of nuclear energy, such as clean air, are important to consumers. (6) Pictures and hand-on demonstrations help in communicating about nuclear energy plants, because many of the discussion concepts are abstract. (7) Trust is crucial and is established now for tomorrow through word and deed. (author)

  6. Advanced integral reactor (SMART) for nuclear desalination

    International Nuclear Information System (INIS)

    At present, severe fresh water shortages are occurring in some regional areas of the Republic of Korea and the problem is expected to spread throughout the country within a decade unless appropriate and timely countermeasures are taken. Of these, nuclear sea water desalination is receiving much attention because the Republic of Korea has a firmly established nuclear environment and abundant sea water resources. In addition, nuclear plants provide cleaner energy than fossil plants, which is another important beneficial factor for countries as crowded as ours. With a view to applying nuclear desalination, development of SMART (system integrated modular advanced reactor) was initiated and is currently in progress. SMART is being developed as a 330 MW(th) integral reactor with passive safety features. The design of SMART is aimed at combining the firmly established commercial reactor design with new advanced technologies. This has led to the use of industry proven Korea optimized fuel assembly (KOFA) based fuels, while radically new technologies such as a self-pressurizing pressurizer, helical once-through steam generators and a new control concept are being developed. The current development status of SMART and its application to nuclear desalination are presented. (author)

  7. Local AREA networks in advanced nuclear reactors

    International Nuclear Information System (INIS)

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

  8. Advances in nuclear science and technology

    CERN Document Server

    Henley, Ernest J

    1975-01-01

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

  9. Computational Design of Advanced Nuclear Fuels

    Energy Technology Data Exchange (ETDEWEB)

    Savrasov, Sergey [Univ. of California, Davis, CA (United States); Kotliar, Gabriel [Rutgers Univ., Piscataway, NJ (United States); Haule, Kristjan [Rutgers Univ., Piscataway, NJ (United States)

    2014-06-03

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

  10. Advanced applications of water cooled nuclear power plants

    International Nuclear Information System (INIS)

    promise shorter construction times and lower capital costs could help to promote a new era of nuclear power. About one-fifth of the world's energy consumption is used for electricity generation. Most of the world's energy consumption is for heat and transportation. Nuclear energy has considerable potential to penetrate these energy sectors now served by fossil fuels that are characterized by price volatility and finite supply. Advanced applications of nuclear energy include seawater desalination, district heating, heat for industrial processes, and electricity and heat for hydrogen production. In addition, since nuclear electricity is generally produced in a base load mode at stable prices, there is considerable near-term potential for nuclear power to contribute to the transportation sector as a carbon-free source of electricity for charging electric and plug-in hybrid vehicles. This collaborative assessment was recommended by the IAEA Nuclear Energy Department's Technical Working Groups on Advanced Technologies for LWRs and HWRs (the TWG-LWR and TWG-HWR). The objective has been to identify opportunities and challenges for water cooled reactors to capture a substantial share of the above mentioned advanced applications. For each application, the opportunities, market context, challenges and potential solutions are addressed

  11. Advanced nuclear reactor public opinion project

    Energy Technology Data Exchange (ETDEWEB)

    Benson, B.

    1991-07-25

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

  12. Advanced nuclear reactor public opinion project

    International Nuclear Information System (INIS)

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

  13. Recent Advances in Ocean Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Kang-Heon Lee

    2015-10-01

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

  14. Equipment system for advanced nuclear fuel development

    International Nuclear Information System (INIS)

    The purpose of the settlement of equipment system for nuclear Fuel Technology Development Facility(FTDF) is to build a seismic designed facility that can accommodate handling of nuclear materials including <20% enriched Uranium and produce HANARO fuel commercially, and also to establish the advanced common research equipment essential for the research on advanced fuel development. For this purpose, this research works were performed for the settlement of radiation protection system and facility special equipment for the FTDF, and the advanced common research equipment for the fuel fabrication and research. As a result, 11 kinds of radiation protection systems such as criticality detection and alarm system, 5 kinds of facility special equipment such as environmental pollution protection system and 5 kinds of common research equipment such as electron-beam welding machine were established. By the settlement of exclusive domestic facility for the research of advanced fuel, the fabrication and supply of HANARO fuel is possible and also can export KAERI-invented centrifugal dispersion fuel materials and its technology to the nations having research reactors in operation. For the future, the utilization of the facility will be expanded to universities, industries and other research institutes

  15. A low noise hybrid preamplifier for nuclear spectroscopy applications

    International Nuclear Information System (INIS)

    Full text: A low noise hybrid preamplifier has been designed and developed successfully in collaboration with BEL, Bangalore. These hybrids are commercially available from BEL, Bangalore with part name as 'BMC 1521'. The hybrids provide flexibility of selecting input JFET, feedback resistor and feedback capacitor, thus making it useful for a wide range of applications in nuclear instrumentation. BMC 1521 based preamplifier has been evaluated using Silicon PIN diode detectors developed by BARC- BEL collaboration and an energy resolution of 2.75 KeV for 60 Ke V gamma rays has been obtained. It is also being used with proportional counter based nuclear spectroscopy applications in BARC. The present paper reports development of the low noise hybrid preamplifier and demonstrates its excellent performance with Si PIN diode detectors

  16. Nuclear-renewable hybrid energy systems: Opportunities, interconnections, and needs

    International Nuclear Information System (INIS)

    Highlights: • We explore nuclear-renewable hybrid energy systems. • They will increase grid flexibility, reduce greenhouse gas emissions, and optimize capital use. • Six aspects of interaction are identified and discussed. • System-level aspects are also discussed. • Gaps and research needs are identified to promote further exploration of the topic. - Abstract: As the U.S. energy system evolves, the amount of electricity from variable-generation sources is likely to increase, which could result in additional times when electricity demand is lower than available production. Thus, purveyors of technologies that traditionally have provided base-load electricity—such as nuclear power plants—can explore new operating procedures to deal with the associated market signals. Concurrently, innovations in nuclear reactor design coupled with sophisticated control systems now allow for more complex apportionment of heat within an integrated system such as one linked to energy-intensive chemical processes. This paper explores one opportunity – nuclear-renewable hybrid energy systems. These are defined as integrated facilities comprised of nuclear reactors, renewable energy generation, and industrial processes that can simultaneously address the need for grid flexibility, greenhouse gas emission reductions, and optimal use of investment capital. Six aspects of interaction (interconnections) between elements of nuclear-renewable hybrid energy systems are identified: Thermal, electrical, chemical, hydrogen, mechanical, and information. Additionally, system-level aspects affect selection, design, and operation of this hybrid system type. Throughout the paper, gaps and research needs are identified to promote further exploration of the topic

  17. Nuclear Hybrid Energy System Modeling: RELAP5 Dynamic Coupling Capabilities

    Energy Technology Data Exchange (ETDEWEB)

    Piyush Sabharwall; Nolan Anderson; Haihua Zhao; Shannon Bragg-Sitton; George Mesina

    2012-09-01

    The nuclear hybrid energy systems (NHES) research team is currently developing a dynamic simulation of an integrated hybrid energy system. A detailed simulation of proposed NHES architectures will allow initial computational demonstration of a tightly coupled NHES to identify key reactor subsystem requirements, identify candidate reactor technologies for a hybrid system, and identify key challenges to operation of the coupled system. This work will provide a baseline for later coupling of design-specific reactor models through industry collaboration. The modeling capability addressed in this report focuses on the reactor subsystem simulation.

  18. Advanced Nuclear Applications in Medicinr at Chiang Mai University

    International Nuclear Information System (INIS)

    The atomic energy applications in Faculty of Medicine, Chiang Mai University (CMU) are mainly performed by department of Radiology that is divided into three dicisions: 1) Diagnostic Radiology Division for the applications of X-rays, ultrasound, and magnetic resonance, 2) Therapeutic Radiology and Oncology Division for cancer treatments by photon accelrator and external radionuclides therapy or brachytherapy, 3) Nuclear Meddicine Division for clinical dignosis by using radionuclide scintigraphy, targeted molecular imaging and internal radionuclide therapy. In the last decade, many advanced medical images for clinical diagnosis included of digital & computed radiology (DR & CR), digital subtraction angiography (DSA) and images (DSI), computed tomography (CT) with dual X-rays energies, manetic resonance imaging (MRI), and hybrid images of SPECT/CT were established in Radiology Department and PET/CT Cyclitron Center Chiang Mai University (PCCMU), respectively. For cancer treatments, the frontier technologies in radiation oncligy therapy such as tomotherapy, IMRT, 3D conformal radiation treatment, stereotactic radiationtherapy (SRT), stereotactic radiation surgery (SRS), and radiation biology laboratory were implemented in the department as well. As far as fast development of nuclear technology in medicine, future implementation of advanced nuclear applications in medicine strongly need an intergrated knoowledge from many specialties e.g. computer softeare in image reconstruction, accuracy and and precision technology, production of specific radiotracers for molecular imaging and therapy, techniques in radionuclide productions, innovation of new wquipment or materials for radiationprotection and safety, etc. However the most important factors of nuclear applications in medicine are the vision, mission and the value statements of the organization on the high cost in radiology investment and human resources development. We have to emphasize that people who are involved

  19. Simulations for the transmutation of nuclear wastes with hybrid reactors

    International Nuclear Information System (INIS)

    A Monte Carlo simulation, devoted to the spallation, has been built in the framework of the hybrid systems proposed for the nuclear wastes incineration. This system GSPARTE, described the reactions evolution. It takes into account and improves the nuclear codes and the low and high energy particles transport in the GEANT code environment, adapted to the geometry of the hybrid reactors. Many applications and abacus useful for the wastes transmutation, have been realized with this system: production of thick target neutrons, source definition, material damages. (A.L.B.)

  20. Recent advances on hybrid approaches for designing intelligent systems

    CERN Document Server

    Melin, Patricia; Pedrycz, Witold; Kacprzyk, Janusz

    2014-01-01

    This book describes recent advances on hybrid intelligent systems using soft computing techniques for diverse areas of application, such as intelligent control and robotics, pattern recognition, time series prediction and optimization complex problems. Soft Computing (SC) consists of several intelligent computing paradigms, including fuzzy logic, neural networks, and bio-inspired optimization algorithms, which can be used to produce powerful hybrid intelligent systems. The book is organized in five main parts, which contain a group of papers around a similar subject. The first part consists of papers with the main theme of type-2 fuzzy logic, which basically consists of papers that propose new models and applications for type-2 fuzzy systems. The second part contains papers with the main theme of bio-inspired optimization algorithms, which are basically papers using nature-inspired techniques to achieve optimization of complex optimization problems in diverse areas of application. The third part contains pape...

  1. Safety related terms for advanced nuclear plants

    International Nuclear Information System (INIS)

    The terms considered in this document are in widespread current use without a universal consensus as to their meaning. Other safety related terms are already defined in national or international codes and standards as well as in IAEA's Nuclear Safety Standards Series. Most of the terms in those codes and standards have been defined and used for regulatory purposes, generally for application to present reactor designs. There is no intention to duplicate the description of such regulatory terms here, but only to clarify the terms used for advanced nuclear plants. The following terms are described in this paper: Inherent safety characteristics, passive component, active component, passive systems, active system, fail-safe, grace period, foolproof, fault-/error-tolerant, simplified safety system, transparent safety

  2. An advanced pitch change mechanism incorporating a hybrid traction drive

    Science.gov (United States)

    Steinetz, B. M.; Loewenthal, S. H.; Sargisson, D. F.; White, G.

    1984-01-01

    A design of a propeller pitch control mechanism is described that meets the demanding requirements of a high-power, advanced turboprop. In this application, blade twisting moment torque can be comparable to that of the main reduction gearbox output: precise pitch control, reliability and compactness are all at a premium. A key element in the design is a compact, high-ratio hybrid traction drive which offers low torque ripple and high torsional stiffness. The traction drive couples a high speed electric motor/alternator unit to a ball screw that actuates the blade control links. The technical merits of this arrangement and the performance characteristics of the traction drive are discussed.

  3. Hybrid and electric advanced vehicle systems (heavy) simulation

    Science.gov (United States)

    Hammond, R. A.; Mcgehee, R. K.

    1981-01-01

    A computer program to simulate hybrid and electric advanced vehicle systems (HEAVY) is described. It is intended for use early in the design process: concept evaluation, alternative comparison, preliminary design, control and management strategy development, component sizing, and sensitivity studies. It allows the designer to quickly, conveniently, and economically predict the performance of a proposed drive train. The user defines the system to be simulated using a library of predefined component models that may be connected to represent a wide variety of propulsion systems. The development of three models are discussed as examples.

  4. Advanced continuously variable transmissions for electric and hybrid vehicles

    Science.gov (United States)

    Loewenthal, S. H.

    1980-01-01

    A brief survey of past and present continuously variable transmissions (CVT) which are potentially suitable for application with electric and hybrid vehicles is presented. Discussion of general transmission requirements and benefits attainable with a CVT for electric vehicle use is given. The arrangement and function of several specific CVT concepts are cited along with their current development status. Lastly, the results of preliminary design studies conducted under a NASA contract for DOE on four CVT concepts for use in advanced electric vehicles are reviewed.

  5. Redefining disease through advances in nuclear medicine

    International Nuclear Information System (INIS)

    Full text: Nuclear Imaging has progressed significantly in the last decade. The disease is being explored at receptor antigenic and biochemical level. The Molecular Imaging with tracers such as the 18-Fluro-Deoxy-Glucose (FDG), 11C-thymidine, 18-Fluro-Estradiol have enabled us to look into different aspects of disease. The FDG helps us in understanding aggressiveness of tumor and thereby survival of a cancer patient. It is enabling us to redefine disease at metabolic level leading to 'Metabolic Classification' of disease. The 18-Fluro-Estradiol scan is exploring breast cancer at receptor level and has enabled us to understand why some breast cancer patients do not respond to the hormone therapy. The 11C-Thymidine scan is able to image proliferative capacity of a tumor and thereby impact on the treatment approach. In addition to the field on oncology, recent advances in Nuclear Imaging are now providing valuable insights in understanding of various other human diseases. We are now redefining Alzheimer's disease and some of the psychiatric illnesses like Schizophrenia and Depression through the new Nuclear Imaging techniques. The years ahead will see extensive application of Nuclear Imaging technology in human disorders. Metabolic Classification of disease would bring out the processes underlying the causation and manifestation of diverse human disorders and help redefine the disease with the aim of more effective and less toxic personalized medicine

  6. Advanced nuclear plants meet the economic challenge

    International Nuclear Information System (INIS)

    Nuclear power plants operated in the baseload regime are economically competitive even when compared with plants burning fossil fuels. As they do not produce emissions when operated, they do not pollute the environment. This is clearly reflected also in the internalized costs. After 2000, many new power plants are expected to be constructed in the USA and worldwide. An important role in this phase will be played by advanced light water reactors of the ABWR and SBWR types representing the future state of the art in technology and safety as well as in cost and plant operations management. (orig.)

  7. Licensed bases management for advanced nuclear plants

    International Nuclear Information System (INIS)

    Prospective Advanced Nuclear Plant (ANP) owners must have high confidence that the integrity of the licensed bases (LB) of a plant will be effectively maintained over its life cycle. Currently, licensing engineers use text retrieval systems, database managers, and checklists to access, update, and maintain vast and disparate licensing information libraries. This paper describes the demonstration of a ''twin-engine'' approach that integrates a program from the emerging class of concept searching tools with a modern Product Data Management System (PDMS) to enhance the management of LB information for an example ANP design. (author)

  8. Advanced Measuring (Instrumentation Methods for Nuclear Installations: A Review

    Directory of Open Access Journals (Sweden)

    Wang Qiu-kuan

    2012-01-01

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

  9. Nuclear-Renewable Hybrid Energy System Market Analysis Plans

    Energy Technology Data Exchange (ETDEWEB)

    Ruth, Mark

    2016-06-09

    This presentation describes nuclear-renewable hybrid energy systems (N-R HESs), states their potential benefits, provides figures for the four tightly coupled N-R HESs that NREL is currently analyzing, and outlines the analysis process that is underway.

  10. Thermochemistry of nuclear fuels in advanced reactors

    International Nuclear Information System (INIS)

    The presence of a large number of elements, accompanied with steep temperature gradient results in dynamic chemistry during nuclear fuel burn-up. Understanding this chemistry is very important for efficient and safe usage of nuclear fuels. The radioactive nature of these fuels puts lot of constraint on regulatory bodies to ensure their accident free operation in the reactors. One of the common aims of advanced fuels is to achieve high burn-up. As burn-up of the fuel increases, chemistry of fission-products becomes increasingly more important. To understand different phenomenon taking place in-pile, many out of-pile experiments are carried out. Extensive studies of thermodynamic properties, phase analysis, thermophysical property evaluation, fuel-fission product clad compatibility are carried out with relevant compounds and simulated fuels (SIMFUEL). All these data are compiled and jointly evaluated using different computational methods to predict fuel behaviour during burn-up. Only when this combined experimental and theoretical information confirms safe operation of the pin, a test pin is prepared and burnt in a test reactor. Every fuel has a different chemistry and different constraints associated with it. In this talk, various thermo-chemical aspects of some of the advanced fuels, mixed carbide, mixed nitride, 'Pu' rich MOX, 'Th' based AHWR fuels and metallic fuels will be discussed. (author)

  11. Next generation advanced nuclear reactor designs

    International Nuclear Information System (INIS)

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

  12. Nuclear Hybrid Energy Systems Regional Studies: West Texas & Northeastern Arizona

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, Humberto E. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Chen, Jun [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kim, Jong Suk [Idaho National Lab. (INL), Idaho Falls, ID (United States); McKellar, Michael George [Idaho National Lab. (INL), Idaho Falls, ID (United States); Deason, Wesley R [Idaho National Lab. (INL), Idaho Falls, ID (United States); Vilim, Richard B. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bragg-Sitton, Shannon M. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Boardman, Richard D. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-04-01

    The primary objective of this study is to conduct a preliminary dynamic analysis of two realistic hybrid energy systems (HES) including a nuclear reactor as the main baseload heat generator (denoted as nuclear HES or nuclear hybrid energy systems [[NHES]) and to assess the local (e.g., HES owners) and system (e.g., the electric grid) benefits attainable by the application of NHES in scenarios with multiple commodity production and high penetration of renewable energy. It is performed for regional cases not generic examples based on available resources, existing infrastructure, and markets within the selected regions. This study also briefly addresses the computational capabilities developed to conduct such analyses, reviews technical gaps, and suggests some research paths forward.

  13. Radioactive waste management and advanced nuclear fuel cycle technologies

    International Nuclear Information System (INIS)

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

  14. Advanced nuclear power plant solidification system

    Energy Technology Data Exchange (ETDEWEB)

    Kikuchi, M. [Hitachi Ltd., Tokyo (Japan); Hirayama, S.; Nishi, T. [Hitachi Ltd., Ibaraki (Japan); Huang, C. T. [Institute of Nuclear Energy Research, Lungtan (Taiwan)

    2003-07-01

    'Slim-Rad' is an advanced radioactive waste treatment system reflecting Hitachi's long experience as a supplier of nuclear plants. The system utilizes new technologies such as a hollow fiber filter, high-performance cement solidification and laundry and shower drain treatment. By adopting this Slim-Rad system, not only the final waste volume but also the number of radwaste tanks can be reduced 1/8 and 1/2, respectively, compared with previous Hitachi radwaste treatment systems. Moreover, release of radioactivity into the environment from the treated waste is reduced effectively. This paper outlines the system and describes its features, as well as the features of the key technology such as volume reduction and solidification technology.

  15. Advances in nuclear and radiochemistry. Extended abstracts

    International Nuclear Information System (INIS)

    The publication compiles extended abstracts of the conference. Conference topics were: fundamental nuclear chemistry (nuclear reactions, radioactive decay), actinides, transactinides, radioanalytics (nuclear and non-nuclear methods), nuclear technology (techniques, cross sections, radionuclide production), radiotracers in life sciences (radiopharmaceutical chemistry), radioactive indicators in research and chemistry, radionuclides in geochemistry and cosmochemistry, nuclear fuel cycle (waste management, transmutation, partitioning), radioecology and environmental sciences. (uke)

  16. Advances in nuclear oil well logging

    International Nuclear Information System (INIS)

    A review is given of some of the significant developments in nuclear logging over the last several years based on publications in scientific journals in the United States and in Europe. Density measurements which make use of the photoelectric effect to distinguish major rock types are now common. Spectral γ-ray measurements of natural radioactivity and neutron-induced radiations make possible elemental analysis from logging data. Familiar logs such as the compensated neutron and density have undergone improvements in data analysis for thin bed identification. Nuclear measurements while drilling have greatly advanced in recent years with the introduction of neutron porosity and γ-ray density measurements in addition to natural γ-ray counting. Multiple radioactive isotopes are now injected into formations and detected by their spectral γ-ray signatures. Computer simulations of logging tool responses have gained wide use in modeling tools and determining their environmental corrections. Monte Carlo codes now routinely run on small computers and parallel processors, whereas they once required large mainframe computers. (Author)

  17. Nuclear integrated database and design advancement system

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-01-01

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

  18. Nuclear integrated database and design advancement system

    International Nuclear Information System (INIS)

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

  19. Advanced nuclear reactor types and technologies

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-07-01

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

  20. Fuels for Advanced Nuclear Energy Systems

    International Nuclear Information System (INIS)

    Fuels for advanced nuclear reactors differ greatly from conventional light water reactor fuels and vary widely between the different concepts, due differences in reactor architecture and deployment. Functional requirements of all fuel designs include (1) retention of fission products and fuel nuclides, (2) dimensional stability, and (3) maintaining a coolable geometry. In all cases, the anticipated fuel performance under normal or off-normal conditions is the limiting factor in reactor system design, and cumulative effects of increased exposure to higher burnup degrades fuel performance. In high-temperature (thermal) gas reactor systems, fuel particles of uranium dioxide or uranium oxycarbide particles are coated with layers of carbon and SiC (or ZrC). Such fuels have been used successfully to very high burnup (10-20% of heavy-metal atoms) and can withstand transient temperatures up to 1600 C. Oxide (pellet-type) and metal (pin-type) fuels clad in stainless steel tubes have been successfully used in liquid metal cooled fast reactors, attaining burnup of 20% or more of heavy-metal atoms. Those fuel designs are being adapted for actinide management missions, requiring greater contents of minor actinides (e.g. Am, Np, Cm). The current status of each fuel system is reviewed and technical challenges confronting the implementation of each fuel in the context of the entire advanced reactor fuel cycle (fabrication, reactor performance, recycle) are discussed

  1. Advanced nuclear reactor types and technologies

    International Nuclear Information System (INIS)

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

  2. ALOHA: an Advanced LOwer Hybrid Antenna coupling code

    International Nuclear Information System (INIS)

    The Advanced LOwer Hybrid Antenna (ALOHA) code, has been developed to improve the modelling of the coupling of lower hybrid (LH) waves from the antenna to a cold inhomogeneous plasma while keeping a fast tool. In contrast to the previous code Slow Wave ANtenna (SWAN) (that only described the interaction of the slow wave between the waveguides and the plasma in a 1D model), the equations are now solved in 2D including the contribution of both the slow and fast waves, with a low computational cost. This approach is completed either by a full-wave computation of the antenna that takes into account its detailed geometry or by a mode-matching code dedicated to multijunctions modelling, which is convenient in preliminary design phases. Moreover, ALOHA can treat more realistic scrape-off layers in front of the antenna, by using a two-layer electron density profile. The ALOHA code has been compared with experimental results from Tore Supra LH antennas of different geometries, as well as benchmarked against other LH coupling codes, with very good results. Once validated, ALOHA has been used as a support for the design of COMPASS and ITER LH antennas and has shown to be a fast and reliable tool for LH antenna design.

  3. ALOHA: an Advanced LOwer Hybrid Antenna coupling code

    Science.gov (United States)

    Hillairet, J.; Voyer, D.; Ekedahl, A.; Goniche, M.; Kazda, M.; Meneghini, O.; Milanesio, D.; Preynas, M.

    2010-12-01

    The Advanced LOwer Hybrid Antenna (ALOHA) code, has been developed to improve the modelling of the coupling of lower hybrid (LH) waves from the antenna to a cold inhomogeneous plasma while keeping a fast tool. In contrast to the previous code Slow Wave ANtenna (SWAN) (that only described the interaction of the slow wave between the waveguides and the plasma in a 1D model), the equations are now solved in 2D including the contribution of both the slow and fast waves, with a low computational cost. This approach is completed either by a full-wave computation of the antenna that takes into account its detailed geometry or by a mode-matching code dedicated to multijunctions modelling, which is convenient in preliminary design phases. Moreover, ALOHA can treat more realistic scrape-off layers in front of the antenna, by using a two-layer electron density profile. The ALOHA code has been compared with experimental results from Tore Supra LH antennas of different geometries, as well as benchmarked against other LH coupling codes, with very good results. Once validated, ALOHA has been used as a support for the design of COMPASS and ITER LH antennas and has shown to be a fast and reliable tool for LH antenna design.

  4. Development of the ITER Advanced Steady State and Hybrid Scenarios

    International Nuclear Information System (INIS)

    Full discharge simulations are performed to examine the plasma current rampup, flattop and rampdown phases self-consistently with the poloidal field (PF) coils and their limitations, plasma transport evolution, and heating/current drive (H/CD) sources. Steady state scenarios are found that obtain 100% non-inductive current with Ip = 7.3-10.0 MA, ΒN ∼ 2.5 for H98 = 1.6, Q's range from 3 to 6, n/nGr = 0.75-1.0, and NB, IC, EC, and LH source have been examined. The scenarios remain within CS/PF coil limits by advancing the pre-magnetization by 40 Wb. Hybrid scenarios have been identified with 35-40% non-inductive current for Ip = 12.5 MA, H98 ∼ 1.25, with q(0) reaching 1 at or after the end of rampup. The equilibrium operating space for the hybrid shows a large range of scenarios can be accommodated, and access 925-1300 s flattop burn durations.

  5. Role of advanced reactors in further nuclear power development

    International Nuclear Information System (INIS)

    As a part of the national long-term nuclear R and D program launched in 1992, an endeavor has been made in Korea to develop advanced nuclear reactor systems with significantly enhanced safety and economics from those of the current generation nuclear power plants. The advanced PWR nuclear reactor systems under development in Korea include 1300 MWe Korean Next Generation Reactor (KNGR), 330 MWt Integral Type System Integrated Modular Advanced Reactor (SMART) for nuclear cogeneration, and 330 MWe Korea Advanced Liquid Metal Reactor (KALIMER) in addition to the evolutionary enhancement of the 1000 MWt KSNPP (Korea Standard Nuclear Power Plant). Three point design philosophy has been adopted for the development of the advanced reactors in Korea : enhancements on safety, economics and public acceptance of nuclear power. To enhance the safety of the advanced reactor systems, a strategy has been adopted to employ advanced design features as well as the passive safety design features. Economically viable design concepts also have been implemented in the evolutionary KSNPP, KNGR, and the SMART development. Economic competitiveness against the fossil plants also has been set as a major objective of the ALWR development program in Korea. These safer and more economical advanced reactors will better promote the public acceptance of the commercial use of the nuclear power and thus could be utilized to meet the forecasted national energy need in the early 21st century. International cooperation in the areas of ALWR development as well as improving public acceptance of the nuclear power is required. (author)

  6. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume VIII. Advanced concepts

    International Nuclear Information System (INIS)

    The goal of the Nonproliferation Alternative Systems Assessment Program has been to provide recommendations for the development and deployment of more proliferation-resistant civilian nuclear-power systems without jeopardizing the development of nuclear energy. In principle, new concepts for nuclear-power systems could be designed so that materials and facilities would be inherently more proliferation-resistant. Such advanced, i.e., less-developed systems, are the subject of this volume. Accordingly, from a number of advanced concepts that were proposed for evaluation, six representative concepts were selected: the fast mixed-spectrum reactor; the denatured molten-salt reactor; the mixed-flow gaseous-core reactor; the linear-accelerator fuel-regenerator reactor; the ternary metal-fueled electronuclear fuel-producer reactor; and the tokamak fusion-fission hybrid reactor

  7. Summary Report of the INL-JISEA Workshop on Nuclear Hybrid Energy Systems

    Energy Technology Data Exchange (ETDEWEB)

    Antkowiak, M.; Ruth, M.; Boardman, R.; Bragg-Sitton, S.; Cherry, R.; Shunn, L.

    2012-07-01

    The Institute for Nuclear Energy Science and Technology (INEST) and the Joint Institute for Strategic Energy Analysis (JISEA) co-sponsored an international workshop to identify research topics important in advancing the potential use of hybrid systems with a specific focus on nuclear-renewable hybrid systems. The workshop included presentations ranging from energy challenges and research and development directions being pursued by nations to multiple options for hybrid systems. Those options include one that is being commercialized to other opportunities and analysis results quantifying them. The workshop also involved two breakout sessions--one focused on thermal energy management issues especially at unit-operation scale and the second focused on system operations issues including system controls, regulatory issues, technical and economic analysis, and market challenges. A discussion involving the full group focused on more general issues such as societal involvement and participation. Key criteria for selecting hybrid energy system projects and metrics for comparing them were also identified by the full group.

  8. Advances in nuclear fuel technology. 3. Development of advanced nuclear fuel recycle systems

    International Nuclear Information System (INIS)

    Fast breeder reactor (FBR) cycle technology has a technical characteristics flexibly easy to apply to diverse fuel compositions such as plutonium, minor actinides, and so on and fuel configurations. By using this characteristics, various feasibilities on effective application of uranium resources based on breeding of uranium of plutonium for original mission of FBR, contribution to radioactive wastes problems based on amounts reduction of transuranium elements (TRU) in high level radioactive wastes, upgrading of nuclear diffusion resistance, extremely upgrading of economical efficiency, and so on. In this paper, were introduced from these viewpoints, on practice strategy survey study on FBR cycle performed by cooperation of the Japan Nuclear Cycle Development Institute (JNC) with electric business companies and so on, and on technical development on advanced nuclear fuel recycle systems carried out at the Central Research Institute of Electric Power Industry, Japan Atomic Energy Research Institute, and so on. Here were explained under a vision on new type of fuels such as nitride fuels, metal fuels, and so on as well as oxide fuels, a new recycle system making possible to use actinides except uranium and plutonium, an 'advanced nuclear fuel cycle technology', containing improvement of conventional wet Purex method reprocessing technology, fuel manufacturing technology, and so on. (G.K.)

  9. The optimization of the combination of various reactors and the important role of fusion-fission hybrid reactors in the development of nuclear energy in China

    International Nuclear Information System (INIS)

    For energy demand in the economic development of China in 21 Century, for seeking the strategy to develop nuclear energy in China, according to the nuclear resources in China and the perspective of international nuclear technology development, the optimization of the combination of three kinds of advanced reactors, namely, HTGR, FBR, and fusion-fission hybrid reactors in the development of nuclear energy in China was investgated. Three alternative stra tegies with different priorities were suggested

  10. SINET3: advanced optical and IP hybrid network

    Science.gov (United States)

    Urushidani, Shigeo

    2007-11-01

    This paper introduces the new Japanese academic backbone network called SINET3, which has been in full-scale operation since June 2007. SINET3 provides a wide variety of network services, such as multi-layer transfer, enriched VPN, enhanced QoS, and layer-1 bandwidth on demand (BoD) services to create an innovative and prolific science infrastructure for more than 700 universities and research institutions. The network applies an advanced hybrid network architecture composed of 75 layer-1 switches and 12 high-performance IP routers to accommodate such diversified services in a single network platform, and provides sufficient bandwidth using Japan's first STM256 (40 Gbps) lines. The network adopts lots of the latest networking technologies, such as next-generation SDH (VCAT/GFP/LCAS), GMPLS, advanced MPLS, and logical-router technologies, for high network convergence, flexible resource assignment, and high service availability. This paper covers the network services, network design, and networking technologies of SINET3.

  11. Single Molecule Techniques for Advanced in situ Hybridization

    Energy Technology Data Exchange (ETDEWEB)

    Hollars, C W; Stubbs, L; Carlson, K; Lu, X; Wehri, E

    2003-02-03

    One of the most significant achievements of modern science is completion of the human genome sequence, completed in the year 2000. Despite this monumental accomplishment, researchers have only begun to understand the relationships between this three-billion-nucleotide genetic code and the regulation and control of gene and protein expression within each of the millions of different types of highly specialized cells. Several methodologies have been developed for the analysis of gene and protein expression in situ, yet despite these advancements, the pace of such analyses is extremely limited. Because information regarding the precise timing and location of gene expression is a crucial component in the discovery of new pharmacological agents for the treatment of disease, there is an enormous incentive to develop technologies that accelerate the analytical process. Here we report on the use of plasmon resonant particles as advanced probes for in situ hybridization. These probes are used for the detection of low levels of gene-probe response and demonstrate a detection method that enables precise, simultaneous localization within a cell of the points of expression of multiple genes or proteins in a single sample.

  12. TALSPEAK Chemistry in Advanced Nuclear Fuel Cycles

    International Nuclear Information System (INIS)

    The separation of trivalent transplutonium actinides from fission product lanthanide ions represents a challenging aspect of advanced nuclear fuel partitioning schemes. The challenge of this separation could be amplified in the context of the AFCI-UREX+1a process, as Np and Pu will accompany the minor actinides to this stage of separation. At present, the baseline lanthanide-actinide separation method is the TALSPEAK (Trivalent Actinide - Lanthanide Separation by Phosphorus reagent Extraction from Aqueous complexes) process. TALSPEAK was developed in the late 1960's at Oak Ridge National Laboratory and has been demonstrated at pilot scale. This process relies on the complex interaction between an organic and an aqueous phase both containing complexants for selectively separating the trivalent actinide. The 3 complexing components are: the di(2-ethylhexyl) phosphoric acid (HDEHP), the lactic acid (HL) and the diethylenetriamine-N,N,N',N'',N''-pentaacetic acid (DTPA). In this report we discuss observations on kinetic and thermodynamic features described in the prior literature and describe some results of our ongoing research on basic chemical features of this system. The information presented indicates that the lactic acid buffer participates in the net operation of the TALSPEAK process in a manner that is not explained by existing information on the thermodynamic features if the known Eu(III)-lactate species. (authors)

  13. MERCURY CONTROL WITH THE ADVANCED HYBRID PARTICULATE COLLECTOR

    Energy Technology Data Exchange (ETDEWEB)

    Stanley J. Miller; Ye Zhuang; Michelle R. Olderbak

    2002-11-01

    This project was awarded under U.S. Department of Energy (DOE) National Energy Technology Laboratory (NETL) Program Solicitation DE-PS26-00NT40769 and specifically addresses Technical Topical Area 4-Testing Novel and Less Mature Control Technologies on Actual Flue Gas at the Pilot Scale. The project team includes the Energy & Environmental Research Center (EERC) as the main contractor; W.L. Gore & Associates, Inc., as a technical and financial partner; and the Big Stone Power Plant operated by Otter Tail Power Company, host for the field-testing portion of the research. Since 1995, DOE has supported development of a new concept in particulate control called the advanced hybrid particulate collector (AHPC). The AHPC has been licensed to W.L. Gore & Associates, Inc., and is now marketed as the ADVANCED HYBRID{trademark} Filter by Gore. The AHPC combines the best features of electrostatic precipitators (ESPs) and baghouses in a unique configuration, providing major synergism between the two collection methods, both in the particulate collection step and in the transfer of dust to the hopper. The AHPC provides ultrahigh collection efficiency, overcoming the problem of excessive fine-particle emissions with conventional ESPs, and it solves the problem of reentrainment and re-collection of dust in conventional baghouses. The AHPC appears to have unique advantages for mercury control over baghouses or ESPs as an excellent gas-solid contactor. The objective of the three-task project is to demonstrate 90% total mercury control in the AHPC at a lower cost than current mercury control estimates. The approach includes bench-scale batch testing that ties the new work to previous results and links results with larger-scale pilot testing with real flue gas on a coal-fired combustion system, pilot-scale testing on a coal-fired combustion system with both a pulse-jet baghouse and an AHPC to prove or disprove the research hypotheses, and field demonstration pilot-scale testing at a

  14. MERCURY CONTROL WITH THE ADVANCED HYBRID PARTICULATE COLLECTOR

    Energy Technology Data Exchange (ETDEWEB)

    Ye Zhuang; Stanley J. Miller; Steven A. Benson; Michelle R. Olderbak

    2003-08-01

    This project was awarded under U.S. Department of Energy (DOE) National Energy Technology Laboratory (NETL) Program Solicitation DE-PS26-00NT40769 and specifically addresses Technical Topical Area 4-Testing Novel and Less Mature Control Technologies on Actual Flue Gas at the Pilot Scale. The project team includes the Energy & Environmental Research Center (EERC) as the main contractor; W.L. Gore & Associates, Inc., as a technical and financial partner; and the Big Stone Plant operated by Otter Tail Power Company, host for the field-testing portion of the research. Since 1995, DOE has supported development of a new concept in particulate control called the advanced hybrid particulate collector (AHPC). The AHPC has been licensed to W.L. Gore & Associates, Inc., and is now marketed as the ''Advanced Hybrid''{trademark} filter by Gore. The AHPC combines the best features of electrostatic precipitators (ESPs) and baghouses in a unique configuration, providing major synergism between the two collection methods, both in the particulate collection step and in the transfer of dust to the hopper. The AHPC provides ultra-high collection efficiency, overcoming the problem of excessive fine-particle emissions with conventional ESPs, and it solves the problem of reentrainment and re-collection of dust in conventional baghouses. The AHPC appears to have unique advantages for mercury control over baghouses or ESPs as an excellent gas-solid contactor. The objective of the three-task project is to demonstrate 90% total mercury control in the AHPC at a lower cost than current mercury control estimates. The approach includes bench-scale batch testing that ties the new work to previous results and links results with larger-scale pilot testing with real flue gas on a coal-fired combustion system, pilot-scale testing on a coal-fired combustion system with both a pulse-jet baghouse and an AHPC to prove or disprove the research hypotheses, and field demonstration pilot

  15. Addressing Attribution - Advances in Nuclear Forensics

    OpenAIRE

    LUETZENKIRCHEN Klaus; Mayer, Klaus; WALLENIUS Maria; Varga, Zsolt

    2012-01-01

    Nuclear forensics is a discipline in science that exploits information which is inherent to nuclear material. As nuclear material is an industrial product, the respective production process will unavoidably leave a "fingerprint" in the material. In consequence, parameters related to process and source material are measured and conclusions about the history and origin of the nuclear material can be drawn. Chemical impurities, microstructure, molecular structure or isotopic composition are exam...

  16. Advanced safeguards for the nuclear renaissance

    Energy Technology Data Exchange (ETDEWEB)

    Miller, Michael C [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory

    2008-01-01

    The global expansion of nuclear energy provides not only the benefit of carbon-neutral electricity, but also the potential for proliferation concern as well. Nuclear safeguards implemented at the state level (domestic) and at the international level by the International Atomic Energy Agency (IAEA) are essential for ensuring that nuclear materials are not misused and are thereby a critical component of the increased usage of nuclear energy. In the same way that the 1950's Atoms for Peace initiative provided the foundation for a robust research and development program in nuclear safeguards, the expansion of nuclear energy that is underway today provides the impetus to enter a new era of technical development in the safeguards community. In this paper, we will review the history of nuclear safeguards research and development as well future directions.

  17. Workshop on advanced nuclear data online services. Summary report

    International Nuclear Information System (INIS)

    This report summarizes the Workshop on Advanced Nuclear Data Online Services held in Vienna, Austria, 29 November to 3 December 1999. It includes the main topics of the agenda, the list of participants, and general comments and recommendations. (author)

  18. Electric and plug-in hybrid vehicles advanced simulation methodologies

    CERN Document Server

    Varga, Bogdan Ovidiu; Moldovanu, Dan; Iclodean, Calin

    2015-01-01

    This book is designed as an interdisciplinary platform for specialists working in electric and plug-in hybrid electric vehicles powertrain design and development, and for scientists who want to get access to information related to electric and hybrid vehicle energy management, efficiency and control. The book presents the methodology of simulation that allows the specialist to evaluate electric and hybrid vehicle powertrain energy flow, efficiency, range and consumption. The mathematics behind each electric and hybrid vehicle component is explained and for each specific vehicle the powertrain

  19. Fuel rod bundles proposed for advanced pressure tube nuclear reactors

    International Nuclear Information System (INIS)

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

  20. MERCURY CONTROL WITH THE ADVANCED HYBRID PARTICULATE COLLECTOR

    International Nuclear Information System (INIS)

    Since 1995, DOE has supported development of a new concept in particulate control, called the advanced hybrid particulate collector (AHPC). The AHPC combines the best features of electrostatic precipitators (ESPs) and baghouses in a unique configuration, providing major synergism between the two collection methods, both in the particulate collection step and in the transfer of dust to the hopper. The AHPC provides ultrahigh collection efficiency, overcoming the problem of excessive fine-particle emission with conventional ESPs, and it solves the problem of reentrainment and re-collection of dust in conventional baghouses. The AHPC appears to have unique advantages for mercury control over baghouses or ESPs as an excellent gas-solid contactor. The objective of the three-task project is to demonstrate 90% total mercury control in the AHPC at a lower cost than current mercury control estimates. The approach includes bench-scale batch testing that ties the new work to previous results and links results with larger-scale pilot testing with real flue gas on a coal-fired combustion system, pilot-scale testing on a coal-fired combustion system with both a pulse-jet baghouse and an AHPC to prove or disprove the research hypotheses, and field demonstration pilot-scale testing at a utility power plant to prove scaleup and demonstrate longer-term mercury control. This project, if successful, will demonstrate at the pilot-scale level a technology that would provide a cost-effective technique to accomplish control of mercury emissions and, at the same time, greatly enhance fine particulate collection efficiency. The technology can be used to retrofit systems currently employing inefficient ESP technology as well as for new construction, thereby providing a solution to a large segment of the U.S. utility industry as well as other industries requiring mercury control

  1. MERCURY CONTROL WITH THE ADVANCED HYBRID PARTICULATE COLLECTOR

    Energy Technology Data Exchange (ETDEWEB)

    Ye Zhuang; Stanley J. Miller; Grant E. Dunham; Michelle R. Olderbak

    2002-02-01

    Since 1995, DOE has supported development of a new concept in particulate control, called the advanced hybrid particulate collector (AHPC). The AHPC combines the best features of electrostatic precipitators (ESPs) and baghouses in a unique configuration, providing major synergism between the two collection methods, both in the particulate collection step and in the transfer of dust to the hopper. The AHPC provides ultrahigh collection efficiency, overcoming the problem of excessive fine-particle emission with conventional ESPs, and it solves the problem of reentrainment and re-collection of dust in conventional baghouses. The AHPC appears to have unique advantages for mercury control over baghouses or ESPs as an excellent gas-solid contactor. The objective of the three-task project is to demonstrate 90% total mercury control in the AHPC at a lower cost than current mercury control estimates. The approach includes bench-scale batch testing that ties the new work to previous results and links results with larger-scale pilot testing with real flue gas on a coal-fired combustion system, pilot-scale testing on a coal-fired combustion system with both a pulse-jet baghouse and an AHPC to prove or disprove the research hypotheses, and field demonstration pilot-scale testing at a utility power plant to prove scaleup and demonstrate longer-term mercury control. This project, if successful, will demonstrate at the pilot-scale level a technology that would provide a cost-effective technique to accomplish control of mercury emissions and, at the same time, greatly enhance fine particulate collection efficiency. The technology can be used to retrofit systems currently employing inefficient ESP technology as well as for new construction, thereby providing a solution to a large segment of the U.S. utility industry as well as other industries requiring mercury control.

  2. Strategy for nuclear wastes incineration in hybrid reactors

    International Nuclear Information System (INIS)

    The transmutation of nuclear wastes in accelerator-driven nuclear reactors offers undeniable advantages. But before going into the detailed study of a particular project, we should (i) examine the possible applications of such systems and (ii) compare the different configurations, in order to guide technological decisions. We propose an approach, answering both concerns, based on the complete description of hybrid reactors. It is possible, with only the transmutation objective and a few technological constraints chosen a posteriori, to determine precisely the essential parameters of such reactors: number of reactors, beam current, size of the core, sub-criticality... The approach also clearly pinpoints the strategic decisions, for which the scientist or engineer is not competent. This global scheme is applied to three distinct nuclear cycles: incineration of solid fuel without recycling, incineration of liquid fuel without recycling and incineration of liquid fuel with on-line recycling; and for two spectra, either thermal or fast. We show that the radiotoxicity reduction with a solid fuel is significant only with a fast spectrum, but the incineration times range from 20 to 30 years. The liquid fuel is appropriate only with on-line recycling, at equilibrium. The gain on the radiotoxicity can be considerable and we describe a number of such systems. The potential of ADS for the transmutation of nuclear wastes is confirmed, but we should continue the description of specific systems obtained through this approach. (author)

  3. Advances in instrumentation for nuclear astrophysics

    Directory of Open Access Journals (Sweden)

    S. D. Pain

    2014-04-01

    Full Text Available The study of the nuclear physics properties which govern energy generation and nucleosynthesis in the astrophysical phenomena we observe in the universe is crucial to understanding how these objects behave and how the chemical history of the universe evolved to its present state. The low cross sections and short nuclear lifetimes involved in many of these reactions make their experimental determination challenging, requiring developments in beams and instrumentation. A selection of developments in nuclear astrophysics instrumentation is discussed, using as examples projects involving the nuclear astrophysics group at Oak Ridge National Laboratory. These developments will be key to the instrumentation necessary to fully exploit nuclear astrophysics opportunities at the Facility for Rare Isotope Beams which is currently under construction.

  4. Advanced training of specialists in nuclear energy at ONPU

    International Nuclear Information System (INIS)

    The is considered the relevance of training of specialists in nuclear energy in the form of advanced training to maintain professional skills at the needed level.The problems of thr re-profiling of specialists working in the nuclear industry and having a non specialized education to the specialty 'Nuclear Engineering' are also considered. The results of activity of the Centre for Continuing Education of ONPU in this direction for recent years are presented.

  5. Options for treatment of legacy and advanced nuclear fuels

    OpenAIRE

    Maher, Christopher John

    2014-01-01

    The treatment of advanced nuclear fuels is relevant to the stabilisation of legacy spent fuels or nuclear materials and fuels from future nuclear reactors. Historically, spent fuel reprocessing has been driven to recover uranium and plutonium for reuse. Future fuel cycles may also recover the minor actinides neptunium, americium and perhaps curium. These actinides would be fabricated into new reactor fuel to produce energy and for transmutation of the minor actinides. This has the potential t...

  6. Spanish program of advanced Nuclear Power Plants

    International Nuclear Information System (INIS)

    The energy Spanish Plan is promoting some actions within the area of advanced reactors. Efforts are focussed onto the European Program of Advanced Reactors, the Program of Passive Plants (EPRI), European Fast Reactor Project and the APWR-1000 Program of INI. Electrical sector utilities and industrial partners supported by the Administration have organized an steering committee. The program of Passive Plants includes activities on Qualification, design and detailed engineering (Qualification project, SBWR project of G.E. and AP600 Project of Westinghouse. The european project on advanced plants has the following Spanish contribution: Analysis of alternative Dossier on European requisites (EUR) and Design of an European Reactor (EPR)

  7. Addressing Attribution - Advances in Nuclear Forensics

    International Nuclear Information System (INIS)

    In nuclear forensic investigations the information is typically used to find out the origin of the material including its production place and process. As nuclear material is an industrial product, the respective production process will unavoidably leave a 'fingerprint' in the material. In consequence, parameters related to process and source material are measured and conclusions about the history and origin of the nuclear material can be drawn. Chemical impurities, microstructure, molecular structure or isotopic composition are examples of such parameters, which compose a characteristic 'signature'. The rare-earth elemental (REE) pattern has been found to be an important signature to determine the type of ore used as source material for the production of uranium ore concentrate, since the REE pattern is invariable in most hydrometallurgical processes. Generally, Decrypting the information for nuclear forensic investigations requires sophisticated methodology, subject matter expertise and reference data. The paper is followed by the slides of the presentation. (A.C.)

  8. Technology Readiness Levels for Advanced Nuclear Fuels and Materials Development

    Energy Technology Data Exchange (ETDEWEB)

    Jon Carmack

    2014-01-01

    The Technology Readiness Level (TRL) process is used to quantitatively assess the maturity of a given technology. The TRL process has been developed and successfully used by the Department of Defense (DOD) for development and deployment of new technology and systems for defense applications. In addition, NASA has also successfully used the TRL process to develop and deploy new systems for space applications. Advanced nuclear fuels and materials development is a critical technology needed for closing the nuclear fuel cycle. Because the deployment of a new nuclear fuel forms requires a lengthy and expensive research, development, and demonstration program, applying the TRL concept to the advanced fuel development program is very useful as a management and tracking tool. This report provides definition of the technology readiness level assessment process as defined for use in assessing nuclear fuel technology development for the Advanced Fuel Campaign (AFC).

  9. Evaluation and development of advanced nuclear materials: IAEA activities

    International Nuclear Information System (INIS)

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

  10. MERCURY CONTROL WITH THE ADVANCED HYBRID PARTICULATE COLLECTOR

    International Nuclear Information System (INIS)

    This project was awarded under U.S. Department of Energy (DOE) Program Solicitation DE-PS26-00NT40769 and specifically addresses Technical Topical Area 4-Testing Novel and Less Mature Control Technologies on Actual Flue Gas at the Pilot-Scale. The project team will include the Energy and Environmental Research Center (EERC) as the main contractor, W.L. Gore and Associates, Inc., as a technical and financial partner, and the Big Stone Power Plant operated by Otter Tail Power Company, which will host the field testing portion of the research. Since 1995, DOE has supported development of a new concept in particulate control, called the advanced hybrid particulate collector (AHPC). The AHPC combines the best features of electrostatic precipitators (ESPs) and baghouses in a unique configuration, providing major synergism between the two collection methods, both in the particulate collection step and in the transfer of dust to the hopper. The AHPC provides ultrahigh collection efficiency, overcoming the problem of excessive fine-particle emission with conventional ESPs, and it solves the problem of reentrainment and re-collection of dust in conventional baghouses. The AHPC appears to have unique advantages for mercury control over baghouses or ESPs as an excellent gas-solid contactor. The objective of the three-task project is to demonstrate 90% total mercury control in the AHPC at a lower cost than current mercury control estimates. The approach includes bench-scale batch testing that ties the new work to previous results and links results with larger-scale pilot testing with real flue gas on a coal-fired combustion system, pilot-scale testing on a coal-fired combustion system with both a pulse-jet baghouse and an AHPC to prove or disprove the research hypotheses, and field demonstration pilot-scale testing at a utility power plant to prove scaleup and demonstrate longer-term mercury control. This project, if successful, will demonstrate at the pilot-scale level a

  11. Development and implementation of advanced control methods for hybrid simulation

    OpenAIRE

    Kim, Hong

    2011-01-01

    Hybrid simulation is an effective way of testing structures that combines the benefits of a computational analysis and experimental testing techniques. Innovative structures consists of state-ofthe-art components and assemblages whose function as a system needs to be tested experimentally. Often times, these components and assemblages push the controller and other testing equipment to its limits. Performing hybrid simulation with the controller in displacement control mode does not always suf...

  12. Perspective of nuclear energy and advanced reactors

    International Nuclear Information System (INIS)

    Future nuclear energy growth will be the result of the contributions of every single plant being constructed or projected at present as it is connected to the grid. As per IAEA, there exists presently 34 nuclear power plants under construction 81 with the necessary permits and funding and 223 proposed, which are plants seriously pursuing permits and financing. This means that in a few decades the number of nuclear power plants in operation will have doubled. This growth rate is characterised by the incorporation of new countries to the nuclear club and the gradually increasing importance of Asian countries. During this expansive phase, generation III and III+designs are or will be used. These designs incorporate the experience from operating plants, and introduce innovations on rationalization design efficiency and safety, with emphasis on passive safety features. In a posterior phase, generation IV designs, presently under development, will be employed. Generation IV consists of several types of reactors (fast reactors, very high temperature reactors, etc), which will improve further sustain ability, economy, safety and reliability concepts. The described situation seems to lead to a renaissance of the nuclear energy to levels hardly thinkable several years ago. (Author)

  13. Once-through hybrid sulfur process for nuclear hydrogen production

    International Nuclear Information System (INIS)

    Increasing concern about the global climate change spurs the development of low- or zero-carbon energy system. Nuclear hydrogen production by water electrolysis would be the one of the short-term solutions, but low efficiency and high production cost (high energy consumption) is the technical hurdle to be removed. In this paper the once-through sulfur process composed of the desulfurization and the water electrolysis systems is proposed. Electrode potential for the conventional water electrolysis (∼2.0 V) can be reduced significantly by the anode depolarization using sulfur dioxide: down to 0.6 V depending on the current density This depolarized electrolysis is the electrolysis step of the hybrid sulfur process originally proposed by the Westinghouse. However; recycling of sulfur dioxide requires a high temperature heat source and thus put another technical hurdle on the way to nuclear hydrogen production: the development of high temperature nuclear reactors and corresponding sulfuric acid decomposition system. By the once-through use of sulfur dioxide rather than the closed recycle, the hurdle can be removed. For the sulfur feed, the desulfurization system is integrated into the water electrolysis system. Fossil fuels include a few percent of sulfur by weight. During the refinement or energy conversion, most of the sulfur should be separated The separated sulfur can be fed to the water electrolysis system and the final product would be hydrogen and sulfuric acid, which is number one chemical in the world by volume. Lowered electrode potential and additional byproduct, the sulfuric acid, can provide economically affordable hydrogen. In this study, the once-through hybrid sulfur process for hydrogen production was proposed and the process was optimized considering energy consumption in electrolysis and sulfuric acid concentration. Economic feasibility of the proposed process was also discussed. Based on currently available experimental data for the electrode

  14. An advanced course in modern nuclear physics

    International Nuclear Information System (INIS)

    The field of nuclear physics is entering the 21st century while experiencing a strong revival. On the one hand it is changing qualitatively through new experimental developments that allow us to direct radioactive and other exotic probes to target nuclei, and spark off extremely energetic nuclear collisions. Also, the impressive sophistication of new detector systems leads us to expect a number of new discoveries in the near future. On the other hand, many new applications have appeared in fields as diverse as medicine, industry, art, archaeology and the environmental sciences. This book is a set of extended lectures on basic and new topics, that gives a tutorial introduction to the field of modern nuclear physics. It is ideally suited to bridging the gap between the standard textbook material and the research literature, and provides the necessary foundation for acting as those who intend to work in any of the many disciplines where nuclear science and technology is going to play an important role in the future. (orig.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-05-15

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

  16. Advances in Nuclear Power Process Heat Applications

    International Nuclear Information System (INIS)

    Following an IAEA coordinated research project, this publication compiles the findings of research and development activities related to practical nuclear process heat applications. An overview of current progress on high temperature gas cooled reactors coupling schemes for different process heat applications, such as hydrogen production and desalination is included. The associated safety aspects are also highlighted. The summary report documents the results and conclusions of the project.

  17. Advances in solid state nuclear track detectors

    International Nuclear Information System (INIS)

    Several types of commercially available phosphate glasses with a wide range of sensitivities have recently been developed. Chief among these is BP-1, which has a high sensitivity and an unprecedented charge resolution. CR-39 has been found to respond differently at velocities below ∼10-2c, where nuclear stopping begins to dominate, than at high velocities, where electronic stopping dominates. Atomic force microscopy has been shown to be a powerful new tool for the study of the etching process, using recoil tracks in mica. CR-39 has been used to set limits on cold fusion rates in strong conflict with rates claimed by some electrochemists. CR-39 and BP-1 have been used to study a number of topics in atomic and nuclear physics including charge pickup in relativistic nucleus-nucleus reactions, nuclear and electromagnetic spallation of relativistic heavy nuclei, the determination of electron attachment and stripping cross sections for relativistic heavy nuclei, and cluster radioactivity. CR-39 is being used to search for strangelets in nature and in ultrarelativistic nucleus-nucleus interactions. Several studies of cosmic ray composition, including TREK, ANTIPODE, HIIS, and UHCRE, are obtaining new results using CR-39, polycarbonate, and BP-1 glass. An experiment to search for weakly interacting massive elementary particles called WIMPs will use mica to detect very short tracks of nuclei that recoil when struck elastically by the WIMPs. (Author)

  18. Advanced hybrid and electric vehicles system optimization and vehicle integration

    CERN Document Server

    2016-01-01

    This contributed volume contains the results of the research program “Agreement for Hybrid and Electric Vehicles”, funded by the International Energy Agency. The topical focus lies on technology options for the system optimization of hybrid and electric vehicle components and drive train configurations which enhance the energy efficiency of the vehicle. The approach to the topic is genuinely interdisciplinary, covering insights from fields. The target audience primarily comprises researchers and industry experts in the field of automotive engineering, but the book may also be beneficial for graduate students.

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

    International Nuclear Information System (INIS)

    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

  20. 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

  1. ADVANCED HYBRID PARTICULATE COLLECTOR - PILOT-SCALE TESTING; TOPICAL

    International Nuclear Information System (INIS)

    A new concept in particulate control, called an advanced hybrid particulate collector (AHPC), is being developed at the Energy and Environmental Research Center (EERC) with U.S. Department of Energy (DOE) funding. In addition to DOE and the EERC, the project team includes W.L. Gore and Associates, Inc., Allied Environmental Technologies, Inc., and the Big Stone power station. The AHPC combines the best features of electrostatic precipitators (ESPs) and baghouses in a unique approach to develop a compact but highly efficient system. Filtration and electrostatics are employed in the same housing, providing major synergism between the two collection methods, both in the particulate collection step and in the transfer of dust to the hopper. The AHPC provides ultrahigh collection efficiency, overcoming the problem of excessive fine-particle emissions with conventional ESPs, and solves the problem of reentrainment and re-collection of dust in conventional baghouses. The objective of the AHPC is to provide and gt;99.99% particulate collection efficiency for particle sizes from 0.01 to 50(micro)m and be applicable for use with all U.S. coals at a lower cost than existing technologies. In previous field tests with the AHPC, some minor bag damage was observed that appeared to be caused by electrical effects. Extensive studies were then carried out to determine the reason for the bag damage and to find possible solutions without compromising AHPC performance. The best solution to prevent the bag damage was found to be perforated plates installed between the electrodes and the bags, which can block the electric field from the bag surface and intercept current to the bags. The perforated plates not only solve the bag damage problem, but also offer many other advantages such as operation at higher A/C (air-to-cloth) ratios, lower pressure drop, and an even more compact geometric arrangement. For this project, AHPC pilot-scale tests were carried out to understand the effect of

  2. Survey of advanced nuclear technologies for potential applications of sonoprocessing.

    Science.gov (United States)

    Rubio, Floren; Blandford, Edward D; Bond, Leonard J

    2016-09-01

    Ultrasonics has been used in many industrial applications for both sensing at low power and processing at higher power. Generally, the high power applications fall within the categories of liquid stream degassing, impurity separation, and sonochemical enhancement of chemical processes. Examples of such industrial applications include metal production, food processing, chemical production, and pharmaceutical production. There are many nuclear process streams that have similar physical and chemical processes to those applications listed above. These nuclear processes could potentially benefit from the use of high-power ultrasonics. There are also potential benefits to applying these techniques in advanced nuclear fuel cycle processes, and these benefits have not been fully investigated. Currently the dominant use of ultrasonic technology in the nuclear industry has been using low power ultrasonics for non-destructive testing/evaluation (NDT/NDE), where it is primarily used for inspections and for characterizing material degradation. Because there has been very little consideration given to how sonoprocessing can potentially improve efficiency and add value to important process streams throughout the nuclear fuel cycle, there are numerous opportunities for improvement in current and future nuclear technologies. In this paper, the relevant fundamental theory underlying sonoprocessing is highlighted, and some potential applications to advanced nuclear technologies throughout the nuclear fuel cycle are discussed. PMID:27400217

  3. Methodology of predicting materials failures in advanced nuclear systems

    International Nuclear Information System (INIS)

    Experiences in the nuclear power plant operation and the fixing of unexpected component failures, originated mainly from corrosion damages, have led to a base methodology of predicting, correcting and preventing failures. Some analogies of the algorithm developed have been extended to the evolution of reliable materials, their testing and database construction in the development of advanced systems for next generation. An illustrative topic was chosen from the materials development and reliability testing carried out in the development of an advanced HTGR for process heat applications. Possibility and issues in making the similar approach in the case of nuclear fusion is also discussed

  4. Human factors aspects of advanced instrumentation in the nuclear industry

    International Nuclear Information System (INIS)

    An important consideration in regards to the use of advanced instrumentation in the nuclear industry is the interface between the instrumentation system and the human. A survey, oriented towards identifying the human factors aspects of digital instrumentation, was conducted at a number of United States (US) and Canadian nuclear vendors and utilities. Human factors issues, subsumed under the categories of computer-generated displays, controls, organizational support, training, and related topics were identified. 20 refs., 2 tabs

  5. Human factors aspects of advanced instrumentation in the nuclear industry

    Energy Technology Data Exchange (ETDEWEB)

    Carter, R.J.

    1989-01-01

    An important consideration in regards to the use of advanced instrumentation in the nuclear industry is the interface between the instrumentation system and the human. A survey, oriented towards identifying the human factors aspects of digital instrumentation, was conducted at a number of United States (US) and Canadian nuclear vendors and utilities. Human factors issues, subsumed under the categories of computer-generated displays, controls, organizational support, training, and related topics were identified. 20 refs., 2 tabs.

  6. Human factors aspects of advanced instrumentation in the nuclear industry

    International Nuclear Information System (INIS)

    This paper reports on an important consideration in regards to the use of advanced instrumentation in the nuclear industry which is the interface between the instrumentation system and the human. A survey, oriented towards identifying the human factors aspects of digital instrumentation, was conducted at a number of United States and Canadian nuclear vendors and utilities. Human factors issues, subsumed under the categories of computer-generated displays, controls, organizational support, training, and related topics were identified

  7. Importance of Advanced Planning of Manufacturing for Nuclear Industry

    Directory of Open Access Journals (Sweden)

    Shykinov Nick

    2016-06-01

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

  8. Advanced materials for space nuclear power systems

    International Nuclear Information System (INIS)

    Research on monolithic refractory metal alloys and on metal matrix composites is being conducted at the NASA Lewis Research Center, Cleveland, Ohio, in support of advanced space power systems. The overall philosophy of the research is to develop and characterize new high-temperature power conversion and radiator materials and to provide spacecraft designers with material selection options and design information. Research on three candidate materials (carbide strengthened niobium alloy PWC-11 for fuel cladding, graphite fiber reinforced copper matrix composites (Gr/Cu) for heat rejection fins, and tungsten fiber reinforced niobium matrix composites (W/NB) for fuel containment and structural supports) considered for space power system applications is discussed. Each of these types of materials offers unique advantages for space power applications

  9. Recent advances in nuclear power plant simulation

    International Nuclear Information System (INIS)

    The field of industrial simulation has experienced very significant progress in recent years, and power plant simulation in particular has been an extremely active area. Improvements may be recorded in practically all simulator subsystems. In Europe, the construction of new full- or optimized-scope nuclear power plant simulators during the middle 1990's has been remarkable intense. In fact, it is possible to identify a distinct simulator generation, which constitutes a new de facto simulation standard. Thomson Training and Simulation has taken part in these developments by designing, building, and validation several of these new simulators for Dutch, German and French nuclear power plants. Their characteristics are discussed in this paper. The following main trends may be identified: Process modeling is clearly evolving towards obtaining engineering-grade performance, even under the added constraints of real-time operation and a very wide range of operating conditions to be covered; Massive use of modern graphic user interfaces (GUI) ensures an unprecedented flexibility and user-friendliness for the Instructor Station; The massive use of GUIs also allows the development of Trainee Stations (TS), which significantly enhance the in-depth training value of the simulators; The development of powerful Software Development Environments (SDE) enables the simulator maintenance teams to keep abreast of modifications carried out in the reference plants; Finally, simulator maintenance and its compliance with simulator fidelity requirements are greatly enhanced by integrated Configuration Management Systems (CMS). In conclusion, the power plant simulation field has attained a strong level of maturity, which benefits its approximately forty years of service to the power generation industry. (author)

  10. Development of advanced nuclear reactors in Russia

    International Nuclear Information System (INIS)

    Several advanced reactor designs have been so far developed in Russia. The AES-91 and AES-92 plants with the VVER-1000 reactors have been developed at the beginning of 1990. However, the former design has been built in China and the latest which is certified meeting European Utility Requirements is being built in India. Moreover, the model VVER-1500 reactor with 50-60 MWd/t burn-up and an enhanced safety was being developed by Gidropress about 2005, excepting to be completed in 2007. But, this schedule has slipped in favor of development of the AES-2006 power plant incorporating a third-generation standardized VVER-1200 reactor of 1170 MWe. This is an evolutionary development of the well-proven VVER-1000 reactor in the AES-92 plant, with longer life, greater power and efficiency and its lead units are being built at Novovoronezh II, to start operation in 2012-13. Based on Atomenergoproekt declaration, the AES-2006 conforms to both Russian standards and European Utility Requirements. The most important features of the AES-2006 design are mentioned as: a design based on the passive safety systems, double containment, longer plant service life of 50 years with a capacity factor of 92%, longer irreplaceable components service life of 60 years, a 28.6% lower amount of concrete and metal, shorter construction time of 54 months, a Core Damage Frequency of 1x10-7/ year and lower liquid and solid wastes by 70% and 80% respectively. The presented paper includes a comparative analysis of technological and safety features, economic parameters and environmental impact of the AES-2006 design versus the other western advanced reactors. Since the Bushehr phase II NPP and several other NPPs are planning in Iran, such analysis would be of a great importance

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

    International Nuclear Information System (INIS)

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

  12. 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.

  13. Strongly coupled inorganic/nanocarbon hybrid materials for advanced electrocatalysis.

    Science.gov (United States)

    Liang, Yongye; Li, Yanguang; Wang, Hailiang; Dai, Hongjie

    2013-02-13

    Electrochemical systems, such as fuel cell and water splitting devices, represent some of the most efficient and environmentally friendly technologies for energy conversion and storage. Electrocatalysts play key roles in the chemical processes but often limit the performance of the entire systems due to insufficient activity, lifetime, or high cost. It has been a long-standing challenge to develop efficient and durable electrocatalysts at low cost. In this Perspective, we present our recent efforts in developing strongly coupled inorganic/nanocarbon hybrid materials to improve the electrocatalytic activities and stability of inorganic metal oxides, hydroxides, sulfides, and metal-nitrogen complexes. The hybrid materials are synthesized by direct nucleation, growth, and anchoring of inorganic nanomaterials on the functional groups of oxidized nanocarbon substrates including graphene and carbon nanotubes. This approach affords strong chemical attachment and electrical coupling between the electrocatalytic nanoparticles and nanocarbon, leading to nonprecious metal-based electrocatalysts with improved activity and durability for the oxygen reduction reaction for fuel cells and chlor-alkali catalysis, oxygen evolution reaction, and hydrogen evolution reaction. X-ray absorption near-edge structure and scanning transmission electron microscopy are employed to characterize the hybrids materials and reveal the coupling effects between inorganic nanomaterials and nanocarbon substrates. Z-contrast imaging and electron energy loss spectroscopy at single atom level are performed to investigate the nature of catalytic sites on ultrathin graphene sheets. Nanocarbon-based hybrid materials may present new opportunities for the development of electrocatalysts meeting the requirements of activity, durability, and cost for large-scale electrochemical applications. PMID:23339685

  14. Hybrid power filter for advanced power quality in industrial systems

    Czech Academy of Sciences Publication Activity Database

    Švec, J.; Müller, Z.; Kasembe, A. G.; Tlustý, J.; Valouch, Viktor

    2013-01-01

    Roč. 103, october 2013 (2013), s. 157-167. ISSN 0378-7796 R&D Projects: GA AV ČR IAA200760703 Institutional research plan: CEZ:AV0Z20570509 Institutional support: RVO:61388998 Keywords : hybrid power filter * power quality * industrial system Subject RIV: JA - Electronic s ; Optoelectronics, Electrical Engineering Impact factor: 1.595, year: 2013 http://www.sciencedirect.com/science/article/pii/S0378779613001417

  15. Hybrid fuel cell bus demonstration: advanced technology moves bus forward

    International Nuclear Information System (INIS)

    The Province of Manitoba has been actively pursuing hydrogen since 2001 as one part of a portfolio of renewable energy alternatives. Six priority hydrogen actions have been underway covering a variety of opportunities, including two recently completed major transit bus and refueling demonstrations. A brief overview of Manitoba's activities on hydrogen will be provided, emphasizing the lessons learned from recent projects such as the hydrogen Hybrid Fuel Cell Bus demonstration, and in particular implications for the research community. (author)

  16. Can we maintain our advanced expertise in nuclear technology?

    International Nuclear Information System (INIS)

    The paper explains why it is important in the light of the Federal Government's plans to wind down nuclear power generation, to provide for governmental or other programmes for ensuring that the advanced expertise in nuclear science and technology in Germany will be maintained well into the future and passed on to the next generation of scientists and (radiation protection) engineers, as a policy to accompany the present Government's plans for a national nuclear power phaseout. The necessity for hedging Germany's high standards and the know-how in nuclear science and technology is explained, not least with respect to protection of the population from the hazards emanating from the operation of nuclear facilities. (orig./CB)

  17. Advanced Research Workshop on Preparedness for Nuclear and Radiological Threats

    CERN Document Server

    Diamond, David; Nuclear Threats and Security Challenges

    2015-01-01

    With the dissolution of the Soviet Union the nuclear threats facing the world are constantly evolving and have grown more complex since the end of the Cold War. The diversion of complete weapon systems or nuclear material to rogue nations and terrorist organizations has increased. The events of the past years have proved the necessity to reevaluate these threats on a level never before considered.  In recognition that no single country possesses all of the answers to the critical scientific, institutional and legal questions associated with combating nuclear and radiological terrorism, the NATO Advanced Research Workshop on “Preparedness for Nuclear and Radiological Threats” and this proceeding was structured to promote wide-ranging, multi-national exploration of critical technology needs and underlying scientific challenges to reducing the threat of nuclear/radiological terrorism; to illustrate through country-specific presentations how resulting technologies were used in national programs; and to outli...

  18. Advanced teleoperation in nuclear applications: consolidated fuel reprocessing program

    International Nuclear Information System (INIS)

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

  19. Cost estimate guidelines for advanced nuclear power technologies

    Energy Technology Data Exchange (ETDEWEB)

    Hudson, C.R. II

    1986-07-01

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

  20. Cost estimate guidelines for advanced nuclear power technologies

    International Nuclear Information System (INIS)

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

  1. Cost estimate guidelines for advanced nuclear power technologies

    International Nuclear Information System (INIS)

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

  2. Advanced nuclear techniques for health and environment

    International Nuclear Information System (INIS)

    Full text: Particle accelerators were developed seventy years ago to investigate nuclear and atomic structure. Nuclear reactors were developed fifty years ago with the promise of producing low cost energy and for military purposes. In the last three decades, we have witnessed a major shift towards the use of high energy ions from accelerators and high quality neutron beams from reactors in the analysis of materials composition and structure for a broad range of scientific applications. Electrostatic accelerators have evolved into specialised tools for accelerator mass spectrometry (AMS) and ion beam analysis techniques. AMS is the technique of choice for the analysis of carbon-14 and other long-lived radionuclides in oceanography, hydrology, paleoclimatology and other environmental applications where isotope sensitivities of one part in 1015 are required. AMS is also applied in toxicology to study human exposure to chemicals and biomolecules at atto mole levels. Synchrotron accelerators fitted with insertion devices like wigglers and ondulators have revived interest in the field of hard x-rays microprobes. Recent developments are based on the use of Fresnel zone plates and tapered glass capillaries producing photon fluxes of 1010 photons per sec per μm2 that allow minimum detection limits below 10-15 g, an ideal microanalytical tool for biology and materials studies. Finally, high-flux neutrons produced by modern research reactors have unique properties for characterising the structure of matter in condensed states. In particular, small angle neutron scattering with cold neutrons is a versatile technique to determine microstructural features with dimensions in the range 10 to 1000 angstroms in biological, environmental and industrial samples. In conclusion, ions, synchrotron radiation and neutron beams are increasingly used to probe materials structure and composition on the microscopic scale, each with their own range of applications, advantages and disadvantages

  3. Advanced I and C systems for nuclear power plants

    International Nuclear Information System (INIS)

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

  4. Advanced I and C systems for nuclear power plants

    International Nuclear Information System (INIS)

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

  5. Advanced Filter Technology For Nuclear Thermal Propulsion

    Science.gov (United States)

    Castillon, Erick

    2015-01-01

    The Scrubber System focuses on using HEPA filters and carbon filtration to purify the exhaust of a Nuclear Thermal Propulsion engine of its aerosols and radioactive particles; however, new technology may lend itself to alternate filtration options, which may lead to reduction in cost while at the same time have the same filtering, if not greater, filtering capabilities, as its predecessors. Extensive research on various types of filtration methods was conducted with only four showing real promise: ionization, cyclonic separation, classic filtration, and host molecules. With the four methods defined, more research was needed to find the devices suitable for each method. Each filtration option was matched with a device: cyclonic separators for the method of the same name, electrostatic separators for ionization, HEGA filters, and carcerands for the host molecule method. Through many hours of research, the best alternative for aerosol filtration was determined to be the electrostatic precipitator because of its high durability against flow rate and its ability to cleanse up to 99.99% of contaminants as small as 0.001 micron. Carcerands, which are the only alternative to filtering radioactive particles, were found to be non-existent commercially because of their status as a "work in progress" at research institutions. Nevertheless, the conclusions after the research were that HEPA filters is recommended as the best option for filtering aerosols and carbon filtration is best for filtering radioactive particles.

  6. An advanced hybrid reprocessing system based on UF6 volatilization and chromatographic separation

    International Nuclear Information System (INIS)

    To recover U, Pu, MA (Np, Am, Cm) and some specific fission products FPs (Cs, Sr, Tc, etc.) from various spent nuclear fuels (LWR/FBR: Oxide, Metal Fuels), we are studying an advanced hybrid reprocessing system based on UF6 volatilization (Pyro) and chromatographic separation (Aqueous). Spent fuels are de-cladded by means of thermal and mechanical methods and then applied to the fluorination/volatilization process, which selectively recovers the most amount of U. Then, the remained fuel components are converted to oxides and dissolved by HNO3 solution. Compared to U, since Pu, MA and FPs are significantly less abundant in spent fuels, the scale of the aqueous separation process could become reasonably small and result in less waste. For the chromatographic separation processes, we have prepared different types of porous silica-based organic/inorganic adsorbents with fast diffusion kinetics, improved chemical stability and low pressure drop in a packed column. So they are advantageously applicable to efficient separation of the actinides and FP elements from the fuel dissolved solution. In this work, adsorption and separation behavior of representative actinides and FP elements was studied. Small scale separation tests using simulated and genuine fuel dissolved solutions were carried out to verify the feasibility of the proposed process. (authors)

  7. Korea advanced nuclear energy system development. Requirements and strategy

    International Nuclear Information System (INIS)

    The requirements for Advanced Nuclear Energy System development in Korea are to improve safety, economics, environmental impact, and social acceptability compared to Korean Next Generation Reactor (KNGR) and to maximize nuclear fuel resource utilization. The target for such system is to commission first commercial unit around 2015. Since Korean R and D and industrial capabilities as well as resources are limited, viable reactor and fuel cycle development strategies have to be analyzed and various good options synthesized to suit for the national, regional, and global needs. Undoubtedly, most viable strategy would be through well balanced joint cooperations of bilateral, or multilateral nature depending upon the progressive stages of advanced nuclear energy system development. (author)

  8. Hybrid reliability model for nuclear reactor safety system

    International Nuclear Information System (INIS)

    The dependability of critical safety systems needs to be quantitatively determined in order to verify their effectiveness, e.g. with regard to regulatory requirements. Since modular redundant safety systems are not required for normal operation, their reliability is strongly dependent on periodic inspection. Several modeling methods for the quantitative assessment of dependability are described in the literature, with a broad variation in complexity and modeling power. Static modeling techniques such as fault tree analysis (FTA) or reliability block diagrams (RBD) are not capable of capturing redundancy and repair or test activities. Dynamic state space based models such as continuous time Markov chains (CTMC) are more powerful but often result in very large, intractable models. Moreover, exponentially distributed state residence times are not a correct representation of actual residence times associated with repair activities or periodic inspection. In this study, a hybrid model combines a system level RBD with a CTMC to describe the dynamics. The effects of periodic testing are modeled by redistributing state probabilities at deterministic test times. Applying the method to the primary safety shutdown system of the BR2(Belgian Reactor 2)—nuclear research reactor, resulted in a quantitative as well as a qualitative assessment of its reliability.

  9. Helium mobility in advanced nuclear ceramics

    International Nuclear Information System (INIS)

    The main goal of this work is to improve our knowledge on the mechanisms able to drive the helium behaviour in transition metal carbides and nitrides submitted to thermal annealing or ion irradiation. TiC, TiN and ZrC polycrystals were implanted with 3 MeV 3He ions at room temperature in the fluence range 2 * 1015 et 6 * 1016 cm-2. Some of them have been pre-irradiated with self-ions (14 MeV Ti or Zr). Fully controlled thermal annealing tests were subsequently carried out in the temperature range 1000 - 1600 C for two hours. The evolution of the helium depth distribution in function of implantation dose, temperature and pre-irradiation dose was measured thanks to the deuteron-induced nuclear reaction 3He(d, p0)4He between 900 keV and 1.8 MeV. The microstructure of implanted and annealed samples was investigated by transmission electron microscopy on thin foils prepared using the FIB technique. Additional characterization tools, as X-ray diffraction and Raman microspectrometry, have been also applied in order to obtain complementary information. Among the most relevant results obtained, the following have to be outlined: - double-peak helium depth profile was measured on as implanted sample for the three compounds. The first peak is located near the end of range and includes the major part of helium, a second peak located close to the surface corresponds to the helium atoms trapped by the native vacancies; - the helium retention capacity in transition metal carbides and nitrides submitted to fully controlled thermal treatments varies according to ZrC0.92 ≤ TiC0.96 ≤ TiN0.96; - whatever the investigated material, a self-ion-induced pre-damaging does not modify the initial helium profile extent. The influence of the post-implantation thermal treatment remains preponderant in any case; - the apparent diffusion coefficient of helium is in the range 4 * 10-18 - 2 * 10-17 m2 s-1 in TiC0.96 and 3.5 * 10-19 - 5.3 * 10-18 m2 s-1 in TiN0.96 between 1100 and 1600 C. The

  10. US DOE Advanced Nuclear Fuel Development Programme Overview

    International Nuclear Information System (INIS)

    The Advanced Fuels Campaign (AFC) has been given the responsibility to develop advanced nuclear fuel technologies for the Department of Energy (DOE) Fuel Cycle Research and Development Program using a science based approach, focusing on developing a microstructural understanding of nuclear fuels and materials. The science based approach combines theory, experiment and multiscale modelling and simulation to develop a fundamental understanding of the fuel fabrication processes and fuel and cladding performance under irradiation. The objective is to use a predictive approach to design fuels and cladding to achieve the desired performance (in contrast to more empirical observation based approaches traditionally used in fuel development). The AFC programme conducts research and development of innovative, enhanced, accident tolerant, next generation LWRs and transmutation fuel systems for sustainable fuel cycles. The major areas of research include enhancing the accident tolerance of fuels and materials, improving the fuel system’s ability to achieve significantly higher fuel and plant performance, and developing innovations that provide for major increases in burnup and performance. The AFC programme is interested in advanced nuclear fuels and materials technologies that are robust, have high performance capability, and are more tolerant to accident conditions than traditional fuel systems. The scope of the AFC includes evaluation and development of multiple fuel forms to support the objectives described in the DOE Strategic Plan and the DOE’s Office of Nuclear Energy Research and Development Roadmap. The word ‘fuel’ is used generically to include fuels, targets and their associated cladding materials. (author)

  11. The advanced test reactor national scientific user facility: advancing nuclear technology education

    International Nuclear Information System (INIS)

    To help ensure the long-term viability of nuclear energy through a robust and sustained research and development effort, the U.S. Department of Energy designated the Idaho National Laboratory (INL) Advanced Test Reactor and associated post-irradiation examination facilities a National Scientific User Facility (ATR NSUF), allowing broader access to nuclear energy researchers. The ATR NSUF provides education programs including a Users Week, internships, faculty student team projects and faculty/staff exchanges. In addition, the ATR NSUF seeks to form strategic partnerships with university facilities that add significant nuclear research capability to the ATR NSUF and are accessible to all ATR NSUF users. (author)

  12. Advances in acrylic-alkyd hybrid synthesis and characterization

    Science.gov (United States)

    Dziczkowski, Jamie

    2008-10-01

    In situ graft acrylic-alkyd hybrid resins were formed by polymerizing acrylic and acrylic-mixed monomers in the presence of alkyds by introduction of a free radical initiator to promote graft formation. Two-dimensional NMR, specifically gradient heteronuclear multiple quantum coherence (gHMQC), was used to clarify specific graft sites of the hybrid materials. Both individual and mixed-monomer systems were produced to determine any individual monomer preferences and to model current acrylic-alkyd systems. Different classes of initiators were used to determine any initiator effects on graft location. The 2D-NMR results confirm grafting at doubly allylic hydrogens located on the fatty acid chains and the polyol segment of the alkyd backbone. The gHMQC spectra show no evidence of grafting across double bonds on either pendant fatty acid groups or THPA unsaturation sites for any of the monomer or mixed monomer systems. It was also determined that choice of initiator has no effect on graft location. In addition, a design of experiments using response surface methodology was utilized to obtain a better understanding of this commercially available class of materials and relate both the chemical and physical properties to one another. A Box-Behnkin design was used, varying the oil length of the alkyd phase, the degree of unsaturation in the polyester backbone, and acrylic to alkyd ratio. Acrylic-alkyd hybrid resins were reduced with an amine/water mixture. Hydrolytic stability was tested and viscoelastic properties were obtained to determine crosslink density. Cured films were prepared and basic coatings properties were evaluated. It was found that the oil length of the alkyd is the most dominant factor for final coatings properties of the resins. Acrylic to alkyd ratio mainly influences the resin properties such as acid number, average molecular weight, and hydrolytic stability. The degree of unsaturation in the alkyd backbone has minimal effects on resin and film

  13. Recent advances in hybrid Cu2O-based heterogeneous nanostructures

    Science.gov (United States)

    Sun, Shaodong

    2015-06-01

    Hybrid Cu2O-based heterogeneous nanostructures possess novel synergistic properties that arise from the integrated interaction between the disparate components, thereby showing promising potential for various important applications including solar cells, carbon monoxide oxidation, photocatalysts, field emission, sensors, templates and so on. With the rapid progress in nanomaterials science and nanotechnology, hybrid Cu2O-based heterogeneous nanostructures with well-controlled compositions, shapes and sizes have been rationally designed and synthesized. This review attempts to summarize the important advances in the development of different types of hybrid Cu2O-based heterogeneous nanostructures, such as hybrid Cu2O-metal nanostructures, hybrid Cu2O-metal oxide nanostructures and hybrid Cu2O-carbon nanostructures. The correlations between the improved performances and interfacial structures of the hybrid Cu2O-based heterogeneous nanostructures are discussed based on some important and representative examples. Several key scientific issues and perspective research directions in this field are also given.

  14. Overview of global development of advanced nuclear power plants

    International Nuclear Information System (INIS)

    Nuclear power has proven its viability as an energy source in many countries. Nuclear power technology is mature, and has achieved tremendous progress in the last decades. Like any other progressing technology, it continues to pursue improvements. The accumulated experience, which now exceeds 14,000 reactor-years of operation, is being used to develop advanced nuclear power plant designs. This development is proceeding for all reactor lines (water-cooled reactors, gas-cooled reactors, and liquid metal-cooled reactors) so that nuclear power can play an important and increasing role in global energy supply in the future. Improved economic competitiveness and a very high level of safety are common goals for advanced designs. To achieve economic competitiveness for new plants, proven means for achieving cost efficiency are being applied and new approaches are being pursued. There is also considerable potential for nuclear energy to expand beyond production of electricity to other applications such as sea-water desalination and hydrogen production. (author)

  15. Advanced nuclear turbojet powerplant characteristics summary for supersonic aircraft

    International Nuclear Information System (INIS)

    The estimated powerplant characteristics of an advanced nuclear powerplant intended for use in a nuclear supersonic manned airplane is contained in this report. This nuclear powerplant consists of a 575 MW, high temperature, lithium-cooled, solid fuel element-type reactor coupled to six turbojet engines especially designed for a supersonic nuclear airplane. The lithium coolant passes from the reactor at 2000F directly to the engine radiators without the use of an intermediate heat exchanger. The engines are fitted with burners enabling the thrust produced by the nuclear powerplant to be augmented by the use of chemical fuel for the take-off, transonic acceleration and landing portions of the flight. The powerplant components have been selected for a maximum thrust-to-weight ratio at Mach 3 and 55,000 feet altitude on nuclear heat only operation compromised for net thrust produced with chemical fuel augmentation during the transonic portion of flight. The power plant data presented, therefore, are primarily applicable to an all supersonic mission on nuclear heat alone. The powerplant data presented in this report are an extension of data contained in PWAC-243, 'NJ-14 All-Nuclear Supersonic Bomber Powerplant Characteristics Summary, March 11, 1958', to a higher reactor power. In addition, the engine compressor pressure ratio has been increased to improve transonic thrust characteristics. Weight data are tabulated for the 575 MW powerplant. The engine envelope based on preliminary radiator size estimates is illustrated. A liquid metal system flow schematic and piping data are included. Shield information including reactor shield outline, assumptions, weights, and direct dose pattern at 50 feet is also included. Estimated performance on nuclear heat only operation and nuclear heat plus burning is presented for an envelope of flight conditions.

  16. Exhibition design: hybrid space of advanced design innovation

    OpenAIRE

    Bollini, L; Borsotti, M

    2014-01-01

    The exhibition design has always been – among other design disciplines – one of the most innovative field of experimentation both for languages and projects improvement. Moreover in the recent years the use of digital technologies, on one hand, and the further more active participation of the public – or, better to say, of the user – on the other hand, are making exhibition design a promising and rising laboratory of advanced innovation. This evolution is shaping itself around the co-particip...

  17. Selection and development of advanced nuclear fuel products

    International Nuclear Information System (INIS)

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

  18. Research advancements and applications of carboranes in nuclear medicinal chemistry

    International Nuclear Information System (INIS)

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

  19. Advanced control room design for nuclear power plants

    International Nuclear Information System (INIS)

    The power industry has seen a continuous growth of size and complexity of nuclear power plants. Accompanying these changes have been extensive regulatory requirements resulting in significant construction, operation and maintenance costs. In response to related concerns raised by industry members, Combustion Engineering developed the NUPLEX 80 Advanced Control Room. The goal of NUPLEX 80TM is to: reduce design and construction costs; increase plant safety and availability through improvements in the man-machine interface; and reduce maintenance costs. This paper provides an overview of the NUPLEX 80 Advanced Control Room and explains how the stated goals are achieved. (author)

  20. Relevance of advanced nuclear fusion research: Breakthroughs and obstructions

    Science.gov (United States)

    Coppi, Bruno

    2016-03-01

    An in depth understanding of the collective modes that can be excited in a wide range of high-energy plasmas is necessary to advance nuclear fusion research in parallel with other fields that include space and astrophysics in particular. Important achievements are shown to have resulted from implementing programs based on this reality, maintaining a tight connection with different areas of investigations. This involves the undertaking of a plurality of experimental approaches aimed at understanding the physics of fusion burning plasmas. At present, the most advanced among these is the Ignitor experiment involving international cooperation, that is designed to investigate burning plasma regimes near ignition for the first time.

  1. Advanced robot vision system for nuclear power plants

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-04-01

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

  3. ADVANCED CERAMIC MATERIALS FOR NEXT-GENERATION NUCLEAR APPLICATIONS

    Energy Technology Data Exchange (ETDEWEB)

    Marra, J.

    2010-09-29

    , and proliferation), the worldwide community is working to develop and deploy new nuclear energy systems and advanced fuel cycles. These new nuclear systems address the key challenges and include: (1) extracting the full energy value of the nuclear fuel; (2) creating waste solutions with improved long term safety; (3) minimizing the potential for the misuse of the technology and materials for weapons; (4) continually improving the safety of nuclear energy systems; and (5) keeping the cost of energy affordable.

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

    International Nuclear Information System (INIS)

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

  5. Japan's advanced reactor development and nuclear fuel policy

    International Nuclear Information System (INIS)

    That being the case, Japan has promoted development and utilization of nuclear energy supply structure in the face of its fragility of its energy supply structure in the face of its growing energy demand, but subject to the strict limitation of adherence to peaceful uses alone as stipulated in its Atomic Energy Basic Law. Furthermore, in order to make the most of limited uranium resources and at the same time solve the problem of appropriate treatment and disposal of reactivate waste from nuclear power generation, Japan has adopted nuclear fuel recycling, i. e. reprocessing of spent nuclear fuel for recovery of plutonium and other reusable components thereof for effective use as nuclear fuel, as one of the basic building blocks of its nuclear energy policy. As an advanced country in the field of peaceful uses of nuclear energy, Japan considers it important that it appropriately respond to growing demands for it to make an international contribution in that field, and that research and development and efforts to resolve common problems be based on international cooperation, and it intends to continue to play an international role in an active manner continue to play an international role in an active manner both in development and utilization of nuclear energy and in nuclear non-proliferation. In particular, concerning the Korean Peninsula Energy Development Organization (KEDO), Japan has high expectations that will function in such a way as to lead to relaxation of tension on the Korean such a way as to lead to relaxation of tension on the Korean Peninsula and more generally in Northeast Asia, and that its activities can be carried forward smoothly on the basis of cooperation among the countries concerned

  6. Advanced ceramic materials for next-generation nuclear applications

    Science.gov (United States)

    Marra, John

    2011-10-01

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

  7. Advanced nuclear plant design options to cope with external events

    International Nuclear Information System (INIS)

    With the stagnation period of nuclear power apparently coming to an end, there is a renewed interest in many Member States in the development and application of nuclear power plants (NPPs) with advanced reactors. Decisions on the construction of several NPPs with evolutionary light water reactors have been made (e.g. EPR Finland for Finland and France) and more are under consideration. There is a noticeable progress in the development and demonstration of innovative high temperature gas cooled reactors, for example, in China, South Africa and Japan. The Generation IV International Forum has defined the International Near Term Deployment programme and, for a more distant perspective, six innovative nuclear energy systems have been selected and certain R and D started by several participating countries. National efforts on design and technology development for NPPs with advanced reactors, both evolutionary and innovative, are ongoing in many Member States. Advanced NPPs have an opportunity to be built at many sites around the world, with very broad siting conditions. There are special concerns that safety of these advanced reactors may be challenged by external events following new scenarios and failure modes, different from those well known for the currently operated reactors. Therefore, the engineering community identified the need to assess the proposed design configurations in relation to external scenarios at the earliest stages of the design development. It appears that an early design optimization in relation to external events is a necessary requirement to achieve safe and economical advanced nuclear power plants. Reflecting on these developments, the IAEA has planned the preparation of a report to define design options for protection from external event impacts in NPPs with evolutionary and innovative reactors. The objective of this publication is to present the state-of-the-art in design approaches for the protection of NPPs with evolutionary and innovative

  8. Advanced ceramic materials for next-generation nuclear applications

    International Nuclear Information System (INIS)

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

  9. 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.

  10. Analysis and synthesis of a hybrid nuclear-solar power plant

    International Nuclear Information System (INIS)

    The article presents a configuration of a Hybrid nuclear-solar power plant with small modular nuclear reactor. The live steam is superheated using molten salts. The molten salts are heated in a solar tower. To ensure continuous work the plant has a high temperature thermal energy storage system. (author)

  11. Station blackout core damage frequency in an advanced nuclear reactor

    International Nuclear Information System (INIS)

    Even though nuclear reactors are provided with protection systems so that they can be automatically shut down in the event of a station blackout, the consequences of this event can be severe. This is because many safety systems that are needed for removing residual heat from the core and for maintaining containment integrity, in the majority of the nuclear power plants, are AC dependent. In order to minimize core damage frequency, advanced reactor concepts are being developed with safety systems that use natural forces. This work shows an improvement in the safety of a small nuclear power reactor provided by a passive core residual heat removal system. Station blackout core melt frequencies, with and without this system, are both calculated. The results are also compared with available data in the literature. (author)

  12. Advanced nuclear reactor public opinion project. Interim report

    Energy Technology Data Exchange (ETDEWEB)

    Benson, B.

    1991-07-25

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

  13. Requirements for advanced simulation of nuclear reactor and chemicalseparation plants.

    Energy Technology Data Exchange (ETDEWEB)

    Palmiotti, G.; Cahalan, J.; Pfeiffer, P.; Sofu, T.; Taiwo, T.; Wei,T.; Yacout, A.; Yang, W.; Siegel, A.; Insepov, Z.; Anitescu, M.; Hovland,P.; Pereira, C.; Regalbuto, M.; Copple, J.; Willamson, M.

    2006-12-11

    This report presents requirements for advanced simulation of nuclear reactor and chemical processing plants that are of interest to the Global Nuclear Energy Partnership (GNEP) initiative. Justification for advanced simulation and some examples of grand challenges that will benefit from it are provided. An integrated software tool that has its main components, whenever possible based on first principles, is proposed as possible future approach for dealing with the complex problems linked to the simulation of nuclear reactor and chemical processing plants. The main benefits that are associated with a better integrated simulation have been identified as: a reduction of design margins, a decrease of the number of experiments in support of the design process, a shortening of the developmental design cycle, and a better understanding of the physical phenomena and the related underlying fundamental processes. For each component of the proposed integrated software tool, background information, functional requirements, current tools and approach, and proposed future approaches have been provided. Whenever possible, current uncertainties have been quoted and existing limitations have been presented. Desired target accuracies with associated benefits to the different aspects of the nuclear reactor and chemical processing plants were also given. In many cases the possible gains associated with a better simulation have been identified, quantified, and translated into economical benefits.

  14. Shielding considerations for advanced space nuclear reactor systems

    International Nuclear Information System (INIS)

    To meet the anticipated future space power needs, the Los Alamos National Laboratory is developing components for a compact, 100 kW/sub e/-class heat pipe nuclear reactor. The reactor uses uranium dioxide (UO2) as its fuel, and is designed to operate around 1500 k. Heat pipes are used to remove thermal energy from the core without the use of pumps or compressors. The reactor heat pipes transfer mal energy to thermoelectric conversion elements that are advanced versions of the converters used on the enormously successful Voyager missions to the outer planets. Advanced versions of this heat pipe reactor could also be used to provide megawatt-level power plants. The paper reviews the status of this advanced heat pipe reactor and explores the radiation environments and shielding requirements for representative manned and unmanned applications

  15. Development of advanced nickel/metal hydride batteries for electric and hybrid vehicles

    Science.gov (United States)

    Gifford, Paul; Adams, John; Corrigan, Dennis; Venkatesan, Srinivasan

    Nickel/metal hydride (Ni/MH) batteries have emerged as the battery technology of choice for electric vehicles. GM Ovonic L.L.C., a joint venture between General Motors and Ovonic Battery was established in 1994 to manufacture and commercialize Ovonic's proprietary Ni/MH batteries for electric and hybrid vehicle applications. GM Ovonic is developing a `family of batteries' aimed at product improvement and cost reduction. Current performance of these new battery designs is described, as well as projections for future improvements. In addition, advances in cell and battery power have allowed further product diversification into cells and batteries specifically designed for a range of hybrid electric vehicles (HEVs).

  16. Fuzzy portfolio optimization advances in hybrid multi-criteria methodologies

    CERN Document Server

    Gupta, Pankaj; Inuiguchi, Masahiro; Chandra, Suresh

    2014-01-01

    This monograph presents a comprehensive study of portfolio optimization, an important area of quantitative finance. Considering that the information available in financial markets is incomplete and that the markets are affected by vagueness and ambiguity, the monograph deals with fuzzy portfolio optimization models. At first, the book makes the reader familiar with basic concepts, including the classical mean–variance portfolio analysis. Then, it introduces advanced optimization techniques and applies them for the development of various multi-criteria portfolio optimization models in an uncertain environment. The models are developed considering both the financial and non-financial criteria of investment decision making, and the inputs from the investment experts. The utility of these models in practice is then demonstrated using numerical illustrations based on real-world data, which were collected from one of the premier stock exchanges in India. The book addresses both academics and professionals pursuin...

  17. Advances in modeling of lower hybrid current drive

    Science.gov (United States)

    Peysson, Y.; Decker, J.; Nilsson, E.; Artaud, J.-F.; Ekedahl, A.; Goniche, M.; Hillairet, J.; Ding, B.; Li, M.; Bonoli, P. T.; Shiraiwa, S.; Madi, M.

    2016-04-01

    First principle modeling of the lower hybrid (LH) current drive in tokamak plasmas is a longstanding activity, which is gradually gaining in accuracy thanks to quantitative comparisons with experimental observations. The ability to reproduce simulatenously the plasma current and the non-thermal bremsstrahlung radial profiles in the hard x-ray (HXR) photon energy range represents in this context a significant achievement. Though subject to limitations, ray tracing calculations are commonly used for describing wave propagation in conjunction with Fokker-Planck codes, as it can capture prominent features of the LH wave dynamics in a tokamak plasma-like toroidal refraction. This tool has been validated on several machines when the full absorption of the LH wave requires the transfer of a small fraction of power from the main lobes of the launched power spectrum to a tail at a higher parallel refractive index. Conversely, standard modeling based on toroidal refraction only becomes more challenging when the spectral gap is large, except if other physical mechanisms may dominate to bridge it, like parametric instabilities, as suggested for JET LH discharges (Cesario et al 2004 Phys. Rev. Lett. 92 175002), or fast fluctuations of the launched power spectrum or ‘tail’ LH model, as shown for Tore Supra (Decker et al 2014 Phys. Plasma 21 092504). The applicability of the heuristic ‘tail’ LH model is investigated for a broader range of plasma parameters as compared to the Tore Supra study and with different LH wave characteristics. Discrepancies and agreements between simulations and experiments depending upon the different models used are discussed. The existence of a ‘tail’ in the launched power spectrum significantly improves the agreement between modeling and experiments in plasma conditions for which the spectral gap is large in EAST and Alcator C-Mod tokamaks. For the Alcator C-Mod tokamak, the experimental evolution of the HXR profiles with density suggests

  18. Characterization of Nuclear and Cytoplasmic Compositions of Somatic Hybrid Plants Between Sweet Orange and Sour Orange

    Institute of Scientific and Technical Information of China (English)

    LIUJi-Hong; XUXiao-Yong; DENGXiu-Xin

    2004-01-01

    Abstract In the present research, flow cytometry (FCM), simple sequence repeat (SSR) and cleavedamplified polymorphic sequence (CAPS) were employed to analyze somatic hybrid plants derived from electrofusion between embryogenic protoplasts of sweet orange (Citrus sinensis Osbeck cv. Shamouti) and leaf-derived protoplasts of sour orange (C. aurantium L). FCM showed that all of the somatic hybrid plants had two-fold fluorescence intensity values of the diploid control, indicating that they were tetraploids. SSR and CAPS were used to characterize the compositions of nuclear and cytoplasmic genomes of the somatic hybnd plants. As for SSR four primer pairs were tried and two showed polymorphisms between the fusion parents. With both pnmer pairs the somatic hybrid plants encompassed DNA bands from both parents, indicating that they were heterokaryonic hybrids. Amplification with some universal primers, followed by digestion with restriction endonucleases, could distinguish the fusion parents from each other. As far as mitochondrial and chloroplast DNA compositions were concerned the somatic hybrid plants shared the same banding patterns as the embryogenic parents for all of the polymorphic primer/enzyme combinations. The results herein demonstrated that the somatic hybrid plants inherited their nuclear genome from both fusion parents, whereas the cytoplasmic genomes were possibly only contributed by the embryogenic parent. Merits of the analytical methods and nuclear and cytoplasmic inheritance of citrus tetraploid somatic hybrids, together with their application, are discussed herein.

  19. A novel hybrid ensemble learning paradigm for nuclear energy consumption forecasting

    International Nuclear Information System (INIS)

    Highlights: ► A hybrid ensemble learning paradigm integrating EEMD and LSSVR is proposed. ► The hybrid ensemble method is useful to predict time series with high volatility. ► The ensemble method can be used for both one-step and multi-step ahead forecasting. - Abstract: In this paper, a novel hybrid ensemble learning paradigm integrating ensemble empirical mode decomposition (EEMD) and least squares support vector regression (LSSVR) is proposed for nuclear energy consumption forecasting, based on the principle of “decomposition and ensemble”. This hybrid ensemble learning paradigm is formulated specifically to address difficulties in modeling nuclear energy consumption, which has inherently high volatility, complexity and irregularity. In the proposed hybrid ensemble learning paradigm, EEMD, as a competitive decomposition method, is first applied to decompose original data of nuclear energy consumption (i.e. a difficult task) into a number of independent intrinsic mode functions (IMFs) of original data (i.e. some relatively easy subtasks). Then LSSVR, as a powerful forecasting tool, is implemented to predict all extracted IMFs independently. Finally, these predicted IMFs are aggregated into an ensemble result as final prediction, using another LSSVR. For illustration and verification purposes, the proposed learning paradigm is used to predict nuclear energy consumption in China. Empirical results demonstrate that the novel hybrid ensemble learning paradigm can outperform some other popular forecasting models in both level prediction and directional forecasting, indicating that it is a promising tool to predict complex time series with high volatility and irregularity.

  20. Research and development of advanced robots for nuclear power plants

    International Nuclear Information System (INIS)

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

  1. 'A la carte' in advanced nuclear energy. Challenges in the 21st Century

    International Nuclear Information System (INIS)

    Here was introduced some parts of advanced efforts in the nuclear energy field recently carried out at universities and institutes in Japan. They have 100 items on summarized advanced nuclear informations, containing 1) new nuclear power generation system and its back-end technologies, 2) nuclear fuels and upgrading on thermal flow technology in reactors, 3) advancement on structural engineering and maintenance engineering of power plants, 4) technical innovation in human man-machine system and robots, 5) advancement of quantum beam engineering and efforts onto realization of nuclear fusion reactors, and 6) safety security on radiation and nuclear energy and their countermeasure to social and environmental problems. (G.K.)

  2. The AMP (Advanced MultiPhysics) Nuclear Fuel Performance code

    International Nuclear Information System (INIS)

    Highlights: ► New, three-dimensional, parallel, multi-physics code to simulate fuel behavior in nominal operation. ► Fully-coupled thermomechanics for nominal operation and operation during transients. ► Isotopic depletion using Scale/ORIGEN-S within a fuel performance code. ► Leveraging of existing, validated material models from existing fuel performance codes. ► Initial validation evaluation of an advanced modeling and simulation code for fuel performance. - Abstract: The AMP (Advanced MultiPhysics) Nuclear Fuel Performance code is a new, three-dimensional, multi-physics tool that uses state-of-the-art solution methods and validated nuclear fuel models to simulate the nominal operation and anticipated operational transients of nuclear fuel. The AMP Nuclear Fuel Performance code leverages existing validated material models from traditional fuel performance codes and the Scale/ORIGEN-S spent-fuel characterization code to provide an initial capability that is shown to be sufficiently accurate for a single benchmark problem and anticipated to be accurate for a broad range of problems. The thermomechanics foundation can be solved in a time-dependent or quasi-static approach with any variation of operator-split or fully-coupled solutions at each time step through interoperable interfaces to leading computational mathematics tools, including PETSc, Trilinos, and SUNDIALS. A baseline validation of the AMP Nuclear Fuel Performance code has been performed through the modeling of an experiment in the Halden Reactor Project (IFA-432) that demonstrates the integrated capability and provides a baseline of the initial accuracy of the software.

  3. Advanced components for electric and hybrid electric vehicles: Proceedings of a workshop

    Energy Technology Data Exchange (ETDEWEB)

    Stricklett, K.L. [ed.; Cookson, A.H.; Bartholomew, R.W.; Leedy, T. [National Inst. of Standards and Tech., Gaithersburg, MD (United States)

    1994-03-01

    This is a key period in the development of electric and hybrid electric vehicles. The landmark 1990 legislation in California requires that two percent of new automobiles be zero emission vehicles in 1998, rising to 10 percent in the year 2005. This can only be met by electric vehicles. The purpose of the workshop was to concentrate on the technologies to improve the design, performance, manufacturability, and economics of the critical components for the next generation of electric and hybrid electric vehicles for the year 2000 and beyond. The workshop began with invited speakers to cover the general topics of impact of the California legislation, federal agency programs, development of standards, infrastructure needs, advanced battery development, and the imperatives for commercial success of electric and hybrid electric vehicles. Working sessions were five parallel meetings on energy conversion systems, energy storage systems, electric propulsion systems, controls and instrumentation, and ancillary systems.

  4. Hybrid systems to address seasonal mismatches between electricity production and demand in nuclear renewable electrical grids

    International Nuclear Information System (INIS)

    A strategy to enable zero-carbon variable electricity production with full utilization of renewable and nuclear energy sources has been developed. Wind and solar systems send electricity to the grid. Nuclear plants operate at full capacity with variable steam to turbines to match electricity demand with production (renewables and nuclear). Excess steam at times of low electricity prices and electricity demand go to hybrid fuel production and storage systems. The characteristic of these hybrid technologies is that the economic penalties for variable nuclear steam inputs are small. Three hybrid systems were identified that could be deployed at the required scale. The first option is the gigawatt-year hourly-to-seasonal heat storage system where excess steam from the nuclear plant is used to heat rock a kilometer underground to create an artificial geothermal heat source. The heat source produces electricity on demand using geothermal technology. The second option uses steam from the nuclear plant and electricity from the grid with high-temperature electrolysis (HTR) cells to produce hydrogen and oxygen. Hydrogen is primarily for industrial applications; however, the HTE can be operated in reverse using hydrogen for peak electricity production. The third option uses variable steam and electricity for shale oil production. -- Highlights: •A system is proposed to meet variable hourly to seasonal electricity demand. •Variable solar and wind electricity sent to the grid. •Base-load nuclear plants send variable steam for electricity and hybrid systems. •Hybrid energy systems can economically absorb gigawatts of variable steam. •Hybrid systems include geothermal heat storage, hydrogen, and shale-oil production

  5. Recent advances in hybrid methods applied to neutral particle transport problems

    International Nuclear Information System (INIS)

    Full text: Particle transport methods are essential for accurate simulation of nuclear systems including nuclear reactors, medical devices, nondestructive interrogation devices, and radiation imaging devices. Commonly, the Monte Carlo and deterministic discrete ordinates (Sn) approaches are used to solve radiation transport problems. Both approaches when used for simulation of large 3-D real-world problems may become inefficient. So, various hybrid methodologies have been developed; these methodologies can be categorized into four groups: coupled deterministic and Monte Carlo methods; Monte Carlo variance reduction using the deterministic importance function; acceleration of the deterministic methods based on a lower-order deterministic formulation; and coupled deterministic methods This paper compares the Sn deterministic and Monte Carlo approaches, reviews different hybrid methodologies, and discusses recent methods we (the University of Florida Transport Theory Group (UFTTG)) have developed and applied to real-world problems. (author)

  6. Mission analysis for hybrid thermionic nuclear reactor LEO-to-GEO transfer applications

    International Nuclear Information System (INIS)

    This paper details the results of mission analyses concerning a hybrid STAR-C based system, which is based on a safe solid fuel form for high-temperature reactor core operation and a rugged planar thermionic energy converter for long-life steady-state electric power production. Hybrid power/propulsion system concepts are shown to offer superior performance capabilities for Low-Earth-Orbit (LEO) to Geosynchronous-Earth-Orbit (GEO) orbital transfer applications over chemical propulsion systems. A key feature of the hybrid power/propulsion system is that the propulsion system uses the on-board payload power system. Mission results for hybrid concepts using Nuclear Thermal Propulsion (NTP), Nuclear Electric Propulsion (NEP), and combination of NTP and NEP are discussed

  7. Hybrid inverse lithography techniques for advanced hierarchical memories

    Science.gov (United States)

    Xiao, Guangming; Hooker, Kevin; Irby, Dave; Zhang, Yunqiang; Ward, Brian; Cecil, Tom; Hall, Brett; Lee, Mindy; Kim, Dave; Lucas, Kevin

    2014-03-01

    greatly improve the ability of ILT to optimize advanced embedded memory designs while retaining significant hierarchy and cell design symmetry, therefore, have good turnaround time and CD uniformity. This paper will explain the enhancements which have been developed in order to overcome the traditional difficulties listed above. These enhancements are in the categories of local CD control, global chip processing options, process window benefit, turn-around time and hierarchy retention.

  8. Basic Principle of Advanced Oxidation Technology : Hybrid Technology Based on Ozone and Titania

    International Nuclear Information System (INIS)

    One of problems in health environment is organic liquid waste from many pollutant resources. Environmental friendly technology for degrading this waste is ozone which produced by plasma discharge technology, but its capability is limited. However, it is needed a new environmental friendly technology which has stronger capability. This new technology is so called advanced oxidation technology. Advanced oxidation technology is a hybrid of ozone, peroxide, UV light and photo catalyst. In this paper, it is introduced basic principle of hybrid of ozone and titania photo catalyst semiconductor. The capability of organic liquid degradation will be stronger because there is new radical which is produced by chemical reaction between electron-hole pair from photo catalyst titania and water or oxygen. This new radical then degrades this organic pollutant. This technology is used to degrade phenol. (author)

  9. A Dual-Stage Hydrothermal Flow Reactor for Green and Sustainable Synthesis of Advanced Hybrid Nanomaterials

    DEFF Research Database (Denmark)

    Hellstern, Henrik Christian Lund

    2016-01-01

    can be synthesized hydrothermally in a dual-stage flow reactor that is both environmentally benign and capable of producing high quantities which is a prerequisite for use in applications. A dual-stage hydrothermal flow reactor was developed for this purpose and used to produce hybrid nanomaterials of...... polycrystalline MoS2 nanosheets. The feasibility of producing supported nanomaterials is demonstrated using TiO2 nanocatalysts on MoS2 sheets This dissertation describes the dual-stage hydrothermal flow reactor and how advanced nanocomposites in high yields may be readily synthesized for potential use in...... control of the nanohybrid morphology. The choice of reactants and temperature profile is shown also to influence whether a composite or mixture is formed. Multiferroic γ-Fe2O3@SrTiO3 is synthesized to demonstrate the feasibility of producing highly advanced nanomaterials in flow. The hybrid is obtained...

  10. Advancements in large-format SiPIN hybrid focal plane technology

    Science.gov (United States)

    Kilcoyne, S.; Malone, N.; Kean, B.; Cantrell, J.; Fierro, J.; Meier, L.; DeWalt, S.; Hewitt, C.; Wyles, J.; Drab, J.; Grama, G.; Paloczi, G.; Vampola, J.; Brown, K.

    2014-09-01

    Raytheon has built hybrid focal planes based on Silicon P-I-N photo-sensors for the past three decades. The device has undergone a continuous improvement process during this period. The detector material has been improved and the thickness has been greatly reduced. Most recently, the readout integrated circuit (ROIC) and the hybridization process, have undergone significant advancements1,2,3. This paper presents recent advancements in the latest generation 8μm pixelpitch 1k2 format and 5k2 format visible Si PIN focal-planes. The current family of devices has very low read-noise ROICs, low detector dark current, operate with a 25 volt bias and deliver 50% mean response operability greater than 99.995%.

  11. The role of ANS in enhancing public understanding of advanced nuclear energy plants

    International Nuclear Information System (INIS)

    Concurrent with the design certification of both evolutionary and passive designs for advanced nuclear energy plants in the US, the American Nuclear Society (ANS) has an extensive nuclear community and public information program under way. The goal of the program is to inform both the technical community and the general public on the following major topics related to the deployment of advanced nuclear energy plants: (1) need for new baseload electrical generation; (2) environmental advantages of nuclear power generation; (3) design of advanced nuclear energy plants; (4) nuclear waste issues; and (5) work force issues

  12. Transient behaviour and coupling aspects of a hybrid MSF-RO nuclear desalination plant

    International Nuclear Information System (INIS)

    BARC is setting up a 6300 M3/day (1.4 MGD) hybrid MSF-RO nuclear desalination plant for sea water desalination at Madras Atomic Power Station (MAPS) coupled to a 170 MWe Pressurised Heavy Water Reactor (PHWR). The transient behaviour and coupling aspects of this dual purpose plant has been discussed. A hybrid desalination plant appears to offer high availability factor. (author)

  13. 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.

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

    International Nuclear Information System (INIS)

    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

  15. Advanced Space Nuclear Reactors from Fiction to Reality

    Science.gov (United States)

    Popa-Simil, L.

    The advanced nuclear power sources are used in a large variety of science fiction movies and novels, but their practical development is, still, in its early conceptual stages, some of the ideas being confirmed by collateral experiments. The novel reactor concept uses the direct conversion of nuclear energy into electricity, has electronic control of reactivity, being surrounded by a transmutation blanket and very thin shielding being small and light that at its very limit may be suitable to power an autonomously flying car. It also provides an improved fuel cycle producing minimal negative impact to environment. The key elements started to lose the fiction attributes, becoming viable actual concepts and goals for the developments to come, and on the possibility to achieve these objectives started to become more real because the theory shows that using the novel nano-technologies this novel reactor might be achievable in less than a century.

  16. Directions for advanced use of nuclear power in century XXI

    Energy Technology Data Exchange (ETDEWEB)

    Walter, C E

    1999-05-01

    Nuclear power can provide a significant contribution to electricity generation and meet other needs of the world and the US during the next century provided that certain directions are taken to achieve its public acceptance. These directions include formulation of projections of population, energy consumption, and energy resources over a responsible period of time. These projections will allow assessment of cumulative effects on the environment and on fixed resources. Use of fossil energy resources in a century of growing demand for energy must be considered in the context of long-term environmental damage and resource depletion. Although some question the validity of these consequences, they can be mitigated by use of advanced fast reactor technology. It must be demonstrated that nuclear power technology is safe, resistant to material diversion for weapon use, and economical. An unbiased examination of all the issues related to energy use, especially of electricity, is an essential direction to take.

  17. Status Report on Structural Materials for Advanced Nuclear Systems

    International Nuclear Information System (INIS)

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

  18. National project : advanced robot for nuclear power plant

    International Nuclear Information System (INIS)

    The national project 'Advanced Robot' has been promoted by the Agency of Industrial science and Technology, MITI for eight years since 1983. The robot for a nuclear plant is one of the projects, and is a prototype intelligent one that also has a three dimensional vision system to generate an environmental model, a quadrupedal walking mechanism to work on stairs and four fingered manipulators to disassemble a valve with a hand tool. Many basic technologies such as an actuator, a tactile sensor, autonomous control and so on progress to high level. The prototype robot succeeded functionally in official demonstration in 1990. More refining such as downsizing and higher intelligence is necessary to realize a commercial robot, while basic technologies are useful to improve conventional robots and systems. This paper presents application studies on the advanced robot technologies. (author)

  19. Ducom 200, a new hybrid gas nuclear approach

    International Nuclear Information System (INIS)

    Full text: Nowadays nuclear energy is facing an increasingly tough competition with other energy sources in many countries. Particularly, in places where gas is available at low prices, combined cycle gas turbine plants (CCGT) appear as formidable competitors against nuclear power plants. The relative cost composition of electric power is different in gas and nuclear generation. In the nuclear industry, operation and maintenance (O and M) and fuel costs are relatively low, while construction costs represent the major component of investment. On the other hand for the CCGT, fuel costs are higher than capital costs. Therefore, the existing relation between the price of gas and the capital cost of nuclear plants mostly determines the economic competitiveness between both technologies, which varies between regions. Recently, a technical analysis was presented in order to complement the advantages of gas turbines and nuclear power plants, leading to a great reduction in energy generation costs. This work presents a new proposal of gas-nuclear synergism, especially focused on the necessities of developing countries. These countries are usually interested in low and medium power nuclear reactors, for energy production and desalinisation. The proposed system is called DUCOM 200, and it has some advantages similar to combined cycle gas turbines, but using present generation LWR Nuclear power plants

  20. Development of once-through hybrid sulfur process for nuclear hydrogen production

    International Nuclear Information System (INIS)

    Humanity has been facing major energy challenges such as the severe climate change, threat of energy security and global energy shortage especially for the developing world. Particularly, growing awareness of the global warming has led to efforts to develop the sustainable energy technologies for the harmony of the economy, social welfare and environment. Water-splitting nuclear hydrogen production is expected to help to resolve those challenges, when high energy efficiency and low cost for hydrogen production become possible. Once-through Hybrid Sulfur process (Ot-HyS), proposed in this work, produces hydrogen using the same SO2 Depolarized water Electrolysis (SDE) process found in the original Hybrid Sulfur cycle (HyS) proposed by Westinghouse, which has the sulfuric acid decomposition (SAD) process using high temperature heat source in order to recover sulfur dioxide for the SDE process. But Ot-HyS eliminated this technical hurdle by replacing it with well-established sulfur combustion process to feed sulfur dioxide to the SDE process. Because Ot-HyS has less technical challenges, Ot-HyS is expected to advance the realization of the large-scale nuclear hydrogen production by feeding an initial nuclear hydrogen stock. Most of the elemental sulfur, at present, is supplied by desulfurization process for environmental reasons during the processing of natural gas and petroleum refining and expected to increase significantly. This recovered sulfur will be burned with oxygen in the sulfur combustion process so that produced sulfur dioxide could be supplied to the SDE process to produce hydrogen. Because the sulfur combustion is a highly exothermic reaction releasing 297 kJ/mol of combustion heat resulting in a large temperature rise, efficiency of the Ot-HyS is expected to be high by recovering this great amount of high grade excess heat with nuclear energy. Sulfuric acid, which is a byproduct of the SDE process, could be sent to the neighboring consumers with or even

  1. Tools for advanced simulations to nuclear propulsion systems in rockets

    Energy Technology Data Exchange (ETDEWEB)

    Torres Sepulveda, A.; Perez Vara, R.

    2004-07-01

    While chemical propulsion rockets have dominated space exploration, other forms of rocket propulsion based on nuclear power, electrostatic and magnetic drive, and other principles besides chemical reactions, have been considered from the earliest days of the field. The goal of most of these advanced rocket propulsion schemes is improved efficiency through higher exhaust velocities, in order to reduce the amount of fuel the rocket vehicle needs to carry, though generally at the expense of high thrust. Nuclear propulsion seems to be the most promising short term technology to plan realistic interplanetary missions. The development of a nuclear electric propulsion spacecraft shall require the development of models to analyse the mission and to understand the interaction between the related subsystems (nuclear reactor, electrical converter, power management and distribution, and electric propulsion) during the different phases of the mission. This paper explores the modelling of a nuclear electric propulsion (NEP) spacecraft type using EcosimPro simulation software. This software is a multi-disciplinary simulation tool with a powerful object-oriented simulation language and state-of-the-art solvers. EcosimPro is the recommended ESA simulation tool for environmental Control and Life Support Systems (ECLSS) and has been used successfully within the framework of the European activities of the International Space Station programme. Furthermore, propulsion libraries for chemical and electrical propulsion are currently being developed under ESA contracts to set this tool as standard usage in the propulsion community. At present, there is not any workable NEP spacecraft, but a standardized-modular, multi-purpose interplanetary spacecraft for post-2000 missions, called ISC-2000, has been proposed in reference. The simulation model presented on this paper is based on the preliminary designs for this spacecraft. (Author)

  2. Nuclear techniques in the development of advanced ceramic technologies

    International Nuclear Information System (INIS)

    The importance of research, development and application of advanced materials is well understood by all developed and most developing countries. Amongst advanced materials, ceramics play a prominent role due to their specific chemical and physical properties. According to performance and importance, advanced ceramics can be classified as structural ceramics (mechanical function) and the so-called functional ceramics. In the latter class of materials, special electrical, chemical, thermal, magnetic and optical properties are of interest. The most valuable materials are multifunctional, for example, when structural ceramics combine beneficial mechanical properties with thermal and chemical sensitivity. Multifunctionality is characteristic of many composite materials (organic/inorganic composite). Additionally, properties of material can be changed by reducing its dimension (thin films, nanocrystalline ceramics). Nuclear techniques, found important applications in research and development of advanced ceramics. The use of neutron techniques has increased dramatically in recent years due to the development of advanced neutron sources, instrumentation and improved data analysis. Typical neutron techniques are neutron diffraction, neutron radiography, small angle neutron scattering and very small angle neutron scattering. Neutrons can penetrate deeply into most materials thus sampling their bulk properties. In determination of the crystal structure of HTSC, YBa2 Cu2O7, XRD located the heavy metal atoms, but failed in finding many of the oxygen atoms, while the neutron diffraction located all atoms equally well in the crystal structure. Neutron diffraction is also unique for the determination of the magnetic structure of materials since the neutrons themselves have a magnetic moment. Application of small angle neutron scattering for the determination of the size of hydrocarbon aggregates within the zeolite channels is illustrated. (author)

  3. Advanced modelling and numerical strategies in nuclear thermal-hydraulics

    International Nuclear Information System (INIS)

    The first part of the lecture gives a brief review of the current status of nuclear thermal hydraulics as it forms the basis of established system codes like TRAC, RELAP5, CATHARE or ATHLET. Specific emphasis is given to the capabilities and limitations of the underlying physical modelling and numerical solution strategies with regard to the description of complex transient two-phase flow and heat transfer conditions as expected to occur in PWR reactors during off-normal and accident conditions. The second part of the lecture focuses on new challenges and future needs in nuclear thermal-hydraulics which might arise with regard to re-licensing of old plants using bestestimate methodologies or the design and safety analysis of Advanced Light Water Reactors relying largely on passive safety systems. In order to meet these new requirements various advanced modelling and numerical techniques will be discussed including extended wellposed (hyperbolic) two-fluid models, explicit modelling of interfacial area transport or higher order numerical schemes allowing a high resolution of local multi-dimensional flow processes.(author)

  4. A nuclear data library production system for advanced lattice codes

    International Nuclear Information System (INIS)

    A nuclear data library production system has been written to recover and format nuclear data required in the recently released advanced lattice code DRAGON Version-4. State-of-the-art resonance self-shielding calculations require information that goes beyond WIMS-D type models. Dilution-dependent cross sections are required for all resonant reactions and for more than 10 specific dilutions. Ultra-fine multigroup cross section data is also required in the resolved energy domain. Another important aspect of advanced lattice codes is the explicit treatment of most neutron induced reactions in the burnup calculation. We need to perform power normalization due to energy from various neutron induced and decay reactions. Even though the decay energy contributes very little relative to the neutron induced reactions, the information will be very useful for post irradiation behavior of fuel. All this information is collected using DRAGR, a new post-processing module in NJOY99, and formatted in a single direct access hierarchical database. Burnup data is also recovered and the short-life isotopic data is automatically lumped. Moreover, PyNjoy, an object-oriented script, was developed to automate the recovery of Endf/B evaluations, the building, and the management of the database. This system was developed under the Lesser General Public License and is openly available. (author)

  5. A VISION of Advanced Nuclear System Cost Uncertainty

    International Nuclear Information System (INIS)

    VISION (VerifIable fuel cycle SImulatiON) is the Advanced Fuel Cycle Initiative's and Global Nuclear Energy Partnership Program's nuclear fuel cycle systems code designed to simulate the US commercial reactor fleet. The code is a dynamic stock and flow model that tracks the mass of materials at the isotopic level through the entire nuclear fuel cycle. As VISION is run, it calculates the decay of 70 isotopes including uranium, plutonium, minor actinides, and fission products. VISION.ECON is a sub-model of VISION that was developed to estimate fuel cycle and reactor costs. The sub-model uses the mass flows generated by VISION for each of the fuel cycle functions (referred to as modules) and calculates the annual cost based on cost distributions provided by the Advanced Fuel Cycle Cost Basis Report1. Costs are aggregated for each fuel cycle module, and the modules are aggregated into front end, back end, recycling, reactor, and total fuel cycle costs. The software also has the capability to perform system sensitivity analysis. This capability may be used to analyze the impacts on costs due to system uncertainty effects. This paper will provide a preliminary evaluation of the cost uncertainty affects attributable to (1) key reactor and fuel cycle system parameters and (2) scheduling variations. The evaluation will focus on the uncertainty on the total cost of electricity and fuel cycle costs. First, a single light water reactor (LWR) using mixed oxide fuel is examined to ascertain the effects of simple parameter changes. Three system parameters; burnup, capacity factor and reactor power are varied from nominal cost values and the affect on the total cost of electricity is measured. These simple parameter changes are measured in more complex scenarios 2-tier systems including LWRs with mixed fuel and fast recycling reactors using transuranic fuel. Other system parameters are evaluated and results will be presented in the paper. Secondly, the uncertainty due to variation

  6. Nuclear hybrid energy systems: imperatives, prospects, and challenges

    International Nuclear Information System (INIS)

    In less than 60 years we have witnessed the transition of nuclear electricity production from an experiment on the high desert of the western United States to more than 430 commercial nuclear power reactors deployed in 31 countries, supplying nearly 14% of all global electricity consumed. The speed at which this transition took place was stunning, as has been the evolution of the technology, business management and operations approach to civil nuclear electricity production. Even as the United States took a two-decade hiatus from the construction of new nuclear electricity plants, other nations embraced the technology and continue to do so. Today, there are 53 nuclear power reactors under construction, 142 planned and 327 proposed for development, including a number in the United States

  7. Bibliography of Connecticut Advanced Nuclear Engineering Laboratory reports

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1965-12-01

    This report, published in two volumes, is a bibliography of the reports published at the Connecticut Advanced Nuclear Engineering Laboratory (CANEL). The reports cover the period 1952 through 1965 and include the Aircraft Nuclear Propulsion program, the Advanced Liquid Metal Cooled Reactor program, the Advanced Reactor Materials program and the SNAP-50 program. The bibliography contains the report number, title, author, date published, and classification. In some cases where the writing of a report was a group effort, and in some reports containing compilations of certain types of data, the author column is not applicable. This is indicated by a {open_quotes}n.a.{close_quotes} in the author column. The following types of reports are included: PWAC`s, TIM`s, CNLM`s, FXM`s and miscellaneous reports. PWAC and TIM reports conform to the requirements of AEC Manual Chapter 3202-041 and 3202-042, respectively. Most of the technical information of interest generated by this project is documented in these reports. CNLM and FXM reports were written primarily for internal distribution. However, these reports contain enough information of technical interest to warrant their inclusion. All CNLM`s and those FXM`s considered to be of interest are included in this bibliography. The MPR`s (Monthly Progress Reports) are the most important of the miscellaneous categories of reports. The other miscellaneous categories relate primarily to equipment and reactor specifications. The Division of Technical Information Extension (DTIE) at Oak Ridge, Tennessee has been designated as the primary recipient of the reports in the CANEL library. When more than one copy of a report was available, the additional copies were delivered to the Lawrence Radiation Laboratory, Livermore, California.

  8. Bibliography of Connecticut Advanced Nuclear Engineering Laboratory reports

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1965-12-01

    This report, published in two, volumes, is a bibliography of the reports published at the Connecticut Advanced Nuclear Engineering Laboratory (CANEL). The reports cover the period 1952 through 1965 and include the Aircraft Nuclear Propulsion program, the Advanced Liquid Metal Cooled Reactor program, the Advanced Reactor Materials program and the SNAP-50 program. The bibliography contains the report number, title, author, date published, and classification. In some cases where the writing of a report was a group effort, and in some reports containing compilations of certain types of data, the author column is not applicable. This is indicated by a {open_quotes}n.a.{close_quotes} in the author column. The following types of reports are included: PWAC`s, TIM`s, CNLM`s. FXM`s and miscellaneous reports. PWAC and TIM reports conform to the requirements of AEC Manual Chapter 3202-041 and 3202-042, respectively. Most of the technical information of interest generated by this project is documented in these reports, CNLM and FXM reports were written primarily for internal distribution. However, these reports contain enough information of technical interest to warrant their inclusion. All CNLM`s and those FXM`s considered to be of interest are included in this bibliography. The MPR`s (Monthly Progress Reports) are the most important of the miscellaneous categories of reports. The other miscellaneous categories relate primarily to equipment and reactor specifications. The Division of Technical Information Extension (DTIE) at Oak Ridge, Tennessee has been designated as the primary recipient of the reports in the CANEL library. When more than one copy of a report was available, the additional copies were delivered to the Lawrence Radiation Laboratory, Livermore, California.

  9. Nuclear Security Research at ANSTO: Advances in Nuclear Forensics and Nuclear Detection

    International Nuclear Information System (INIS)

    The Australian Nuclear Science and Technology Organisation (ANSTO) supports Australia’s nuclear security needs by providing trusted advice to government, supplying technical expertise and operational support and undertaking scientific research to support the next generation of innovation. In the past 10 years ANSTO’s notable achievements in nuclear security have included international leadership in the establishment of the scientific discipline of nuclear forensics, profiling of Australia’s uranium ore concentrates, development of border security technologies, such as the AUS series X-ray Test Pieces and radionuclide identification algorithms, as well as the provision of advice and analytical services to government and partner agencies. This presentation will outline ANSTO’s current work, progress and recent successes in nuclear forensics and nuclear detection. (author)

  10. Environmental performance of advanced hybrid energy storage systems for electric vehicle applications

    International Nuclear Information System (INIS)

    Highlights: • The environmental impact of advanced energy storage systems is assessed. • The methodology used is Life Cycle Assessment following the ISO 14040 and 14044. • Twelve impact categories are assessed to avoid burden shifting. • Increasing the efficiency and extending the lifetime benefits the environmental performance. • The results show that there are hot spots where to act and reduce the overall impact. - Abstract: In this paper the environmental performance of an advanced hybrid energy storage system, comprising high power and high energy lithium iron phosphate cells, is compared with a stand alone battery concept composed of lithium manganese oxide cells. The methodology used to analyse the environmental impacts is Life Cycle Assessment (LCA). The manufacturing, use phase and end-of-life of the battery packs are assessed for twelve impact categories. The functional unit is 1 km driven under European average conditions. The present study assesses the environmental performance of the two battery packs for two scenarios: scenario 1 with a vehicle total drive range of 150,000 km and scenario 2 with total driving range of the car of 300,000 km. The results of scenario 1 show that the increased efficiency of the hybrid system reduces, in general, the environmental impact during the use stage, although the manufacturing stage has higher impact than the benchmark. Scenario 2 shows how the extended lifetime of the hybrid system benefits the emissions per km driven

  11. Hybrid fixation in the bilateral sagittal split osteotomy for lower jaw advancement

    Directory of Open Access Journals (Sweden)

    Felipe Ladeira Pereira

    2010-02-01

    Full Text Available Miniplate and screw fixation has been widely used in bilateral sagittal split osteotomy, but some issues remain unclear concerning its lack of rigidity when compared to Spiessl's bicortical technique. This paper demonstrates the hybrid fixation technique in a case report. A 34-year-old female patient underwent a double jaw surgery with counter-clockwise rotation of the mandible fixed using the hybrid fixation technique. The patient evolved well in the postoperative period and is still under follow up after 14 months, reporting satisfaction with the results and no significant deviation from the treatment plan up to now. No damage to tooth roots was done, maxillomandibular range of motion was within normality and regression of the inferior alveolar nerve paresthesia was observed bilaterally. The hybrid mandibular fixation is clearly visible in the panoramic and cephalometric control radiographs. It seems that the hybrid fixation can sum the advantages of both monocortical and bicortical techniques in lower jaw advancement, increasing fixation stability without significant damage to the mandibular articulation and the inferior alveolar nerve. A statistical investigation seems necessary to prove its efficacy.

  12. Bridging the gap: adapting advanced display technologies for use in hybrid control rooms

    International Nuclear Information System (INIS)

    has recently assisted INL in establishing the technical infrastructure for implementation of HSI prototypes from HAMMLAB into the HSSL to demonstrate relevant control room replacement systems in support of the LWRS program. In March, 2014, IFE delivered the first HSI prototype utilizing this infrastructure - a large screen overview display for INL's simulator. The co-operation now continues by developing Procedure Support Displays targeted for operators in hybrid control room settings. These prototypes are being validated with U.S. reactor operators in the HSSL and optimized to enhance their performance. This research serves as a crucial stepping stone toward incorporation of advanced display technologies into conventional main control rooms.

  13. Bridging the gap: adapting advanced display technologies for use in hybrid control rooms

    Energy Technology Data Exchange (ETDEWEB)

    Jokstad, Håkon [Inst. for Energy Technology, Halden (Norway); Boring, Ronald [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-02-01

    recently assisted INL in establishing the technical infrastructure for implementation of HSI prototypes from HAMMLAB into the HSSL to demonstrate relevant control room replacement systems in support of the LWRS program. In March, 2014, IFE delivered the first HSI prototype utilizing this infrastructure — a large screen overview display for INL's simulator. The co-operation now continues by developing Procedure Support Displays targeted for operators in hybrid control room settings. These prototypes are being validated with U.S. reactor operators in the HSSL and optimized to enhance their performance. This research serves as a crucial stepping stone toward incorporation of advanced display technologies into conventional main control rooms.

  14. Nuclear energy and fusion-fission hybrid reactor for pure energy production

    International Nuclear Information System (INIS)

    The next two decades are very critical for nuclear energy development. The commercial fast reactor may be in use around 2035; it is also possible that magnetically confined fusion, laser fusion and z-pinch fusion will be demonstrated at that time. A fusion demonstration reactor can be a pure fusion or a fusion-fission hybrid. The latter can lower the fusion power and mitigate the radiation damage of high energy neutrons to materials. On the other hand, the supply of deuterium and tritium as fuel for fusion can only last a few hundred years. We describe here a hybrid for pure energy use which can make full use of uranium and is proliferation resistant, as no separation of uranium and plutonium is needed in post-processing. The union of fission, fusion, and a pure energy hybrid can contribute to the large scale use of nuclear energy in the near future, and supply mankind for more than a thousand years. (authors)

  15. Coupling of RO-MSF hybrid desalination plants with nuclear reactors

    International Nuclear Information System (INIS)

    Full text.Reverse osmosis (RO) and multistage flash (MSF) desalination are the most widely commercial available processes. MSF utilizes stream in the brine heater as a primary source of energy. RO is derived mainly by electricity that pumps the feed water against the mambranes. Steam and electricity and be produced easily by nuclear reactors. Nuclear reactors may be coupled with deslination plants (MSF, RO or combined (hybrid) RO/MSF configuration). This integrated plant will be capable of producing power and water at reasonable cost. The capital and operating cost will be reduced and the excess power can be efficiently utilized. Maintenance and operating cost will drop significantly. In this paper, a techno-economic study of hybrid reverses osmosis /multistage flash desalination will be carried. The proposed configuration (hybrid RO/MSF) coupled with nuclear reactor is considered the most appropriate candidate system for the application of dual-purpose nuclear desalination plants. the design parameters for such a desalination hybrid system will be the applied pressure and recovery for reverse osmosis plant and the number of stages and the heat transfer areas for multistage flash plant

  16. Optimization of an Advanced Hybrid Wing Body Concept Using HCDstruct Version 1.2

    Science.gov (United States)

    Quinlan, Jesse R.; Gern, Frank H.

    2016-01-01

    Hybrid Wing Body (HWB) aircraft concepts continue to be promising candidates for achieving the simultaneous fuel consumption and noise reduction goals set forth by NASA's Environmentally Responsible Aviation (ERA) project. In order to evaluate the projected benefits, improvements in structural analysis at the conceptual design level were necessary; thus, NASA researchers developed the Hybrid wing body Conceptual Design and structural optimization (HCDstruct) tool to perform aeroservoelastic structural optimizations of advanced HWB concepts. In this paper, the authors present substantial updates to the HCDstruct tool and related analysis, including: the addition of four inboard and eight outboard control surfaces and two all-movable tail/rudder assemblies, providing a full aeroservoelastic analysis capability; the implementation of asymmetric load cases for structural sizing applications; and a methodology for minimizing control surface actuation power using NASTRAN SOL 200 and HCDstruct's aeroservoelastic finite-element model (FEM).

  17. Impact of Nuclear Energy Futures on Advanced Fuel Cycle Options

    International Nuclear Information System (INIS)

    tripling market share by 2100 from the current 8.4% to 25%, equivalent to continuing the average market growth of last 50 years for an additional 100 years. Five primary spent fuel management strategies are assessed against each of the energy futures to determine the number of geological repositories needed and how the first repository would be used. The geological repository site at Yucca Mountain, Nevada, has the physical potential to accommodate all the spent fuel that will be generated by the current fleet of domestic commercial nuclear reactors, even with license extensions. If new nuclear plants are built in the future as replacements or additions, the United States will need to adopt spent fuel treatment to extend the life of the repository. Should a significant number of new nuclear plants be built, advanced fuel recycling will be needed to fully manage the spent fuel within a single repository. The analysis also considers the timeframe for most efficient implementation of new spent fuel management strategies. The mix of unprocessed spent fuel and processed high level waste in Yucca Mountain varies with each future and strategy. Either recycling must start before there is too much unprocessed waste emplaced or unprocessed waste will have to be retrieved later with corresponding costs. For each case, the latest date to implement reprocessing without subsequent retrieval is determined

  18. Improving human reliability through better nuclear power plant system design: Program for advanced nuclear power studies

    International Nuclear Information System (INIS)

    The project on ''Development of a Theory of the Dependence of Human Reliability upon System Designs as a Means of Improving Nuclear Power Plant Performance'' was been undertaken in order to address the problem of human error in advanced nuclear power plant designs. Lack of a mature theory has retarded progress in reducing likely frequencies of human errors. Work being pursued in this project is to perform a set of experiments involving human subjects who are required to operate, diagnose and respond to changes in computer-simulated systems, relevant to those encountered in nuclear power plants, which are made to differ in complexity in a systematic manner. The computer program used to present the problems to be solved also records the response of the operator as it unfolds

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

    International Nuclear Information System (INIS)

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

  20. Experiences and Trends of Manufacturing Technology of Advanced Nuclear Fuels

    International Nuclear Information System (INIS)

    The 'Atoms for Peace' mission initiated in the mid-1950s paved the way for the development and deployment of nuclear fission reactors as a source of heat energy for electricity generation in nuclear power reactors and as a source of neutrons in non-power reactors for research, materials irradiation, and testing and production of radioisotopes. The fuels for nuclear reactors are manufactured from natural uranium (∼99.3% 238U + ∼0.7% 235U) and natural thorium (∼100% 232Th) resources. Currently, most power and research reactors use 235U, the only fissile isotope found in nature, as fuel. The fertile isotopes 238U and 232Th are transmuted in the reactor to human-made 239Pu and 233U fissile isotopes, respectively. Likewise, minor actinides (MA) (Np, Am and Cm) and other plutonium isotopes are also formed by a series of neutron capture reactions with 238U and 235U. Long term sustainability of nuclear power will depend to a great extent on the efficient, safe and secure utilization of fissile and fertile materials. Light water reactors (LWRs) account for more than 82% of the operating reactors, followed by pressurized heavy water reactors (PHWRs), which constitute ∼10% of reactors. LWRs will continue to dominate the nuclear power market for several decades, as long as economically viable natural uranium resources are available. Currently, the plutonium obtained from spent nuclear fuel is subjected to mono recycling in LWRs as uranium-plutonium mixed oxide (MOX), containing up to 12% PuO2, in a very limited way. The reprocessed uranium (RepU) is also re-enriched and recycled in LWRs in a few countries. Unfortunately, the utilization of natural uranium resources in thermal neutron reactors is 2 and MOX fuel technology has matured during the past five decades. These fuels are now being manufactured, used and reprocessed on an industrial scale. Mixed uranium- plutonium monocarbide (MC), mononitride (MN) and U-Pu-Zr alloys are recognized as advanced fuels for sodium

  1. 77 FR 3009 - Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Advanced Boiling Water Reactors

    Science.gov (United States)

    2012-01-20

    ...The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft NUREG, NUREG-2104, Revision 0, ``Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Advanced Boiling Water...

  2. Advanced control approach for hybrid systems based on solid oxide fuel cells

    International Nuclear Information System (INIS)

    Highlights: • Advanced new control system for SOFC based hybrid plants. • Proportional–Integral approach with feed-forward technology. • Good control of fuel cell temperature. • All critical properties maintained inside safe conditions. - Abstract: This paper shows a new advanced control approach for operations in hybrid systems equipped with solid oxide fuel cell technology. This new tool, which combines feed-forward and standard proportional–integral techniques, controls the system during load changes avoiding failures and stress conditions detrimental to component life. This approach was selected to combine simplicity and good control performance. Moreover, the new approach presented in this paper eliminates the need for mass flow rate meters and other expensive probes, as usually required for a commercial plant. Compared to previous works, better performance is achieved in controlling fuel cell temperature (maximum gradient significantly lower than 3 K/min), reducing the pressure gap between cathode and anode sides (at least a 30% decrease during transient operations), and generating a higher safe margin (at least a 10% increase) for the Steam-to-Carbon Ratio. This new control system was developed and optimized using a hybrid system transient model implemented, validated and tested within previous works. The plant, comprising the coupling of a tubular solid oxide fuel cell stack with a microturbine, is equipped with a bypass valve able to connect the compressor outlet with the turbine inlet duct for rotational speed control. Following model development and tuning activities, several operative conditions were considered to show the new control system increased performance compared to previous tools (the same hybrid system model was used with the new control approach). Special attention was devoted to electrical load steps and ramps considering significant changes in ambient conditions

  3. Results of nuclear design accuracy evaluation on BN-600 hybrid core

    International Nuclear Information System (INIS)

    Nuclear design accuracy on the BN-600 hybrid core has been evaluated using the JNC's nuclear analysis system for FBR cores, by utilizing the critical experiment analysis results on BFS-62 configuration that had been obtained under JNC's efforts for Russian surplus weapons plutonium disposition. In the BN-600 hybrid core design, a part of the current UO2 fuel region is replaced by MOX fuel, and the peripheral blanket region by stainless steel reflectors, respectively. These changes were simulated in a series of critical experiment configurations (BFS-62-1 to 4). Based on the analysis results on both BFS-62 configurations and other fast reactor cores, nuclear design accuracy on the BN-600 hybrid core has been evaluated by applying both the group constant adjustment method and the bias method. Evaluated nuclear parameters include, the ciriticality, fission rate distribution, sodium void reactivity, control rod worth, burn-up reactivity loss, etc. It is concluded, by applying the group constant adjustment method, that the evaluated accuracy (uncertainty) of most of the nuclear parameters can be decreased to less than half of those based on the basic nuclear constant without reflecting any experimental data. The improvement was mainly achieved by reducing the covariance of the iron elastic cross section. This significant effect results from the feature of the BN-600 hybrid core, which has relatively larger power density, adopts U235 as the main fissile nuclide, and has the stainless steel reflector surrounding the fuel region. In addition, good consistency of analysis results between the BFS and other fast reactor cores is confirmed. Information obtained by BFS-62 experiment show significant contribution to the accuracy improvement. It is also found that the bias method shows less significant effects on the accuracy improvement than the group constant adjustment method. Furthermore, the bias method may degrade the accuracy for certain nuclear parameters that have large

  4. Advanced Electrical Machines and Machine-Based Systems for Electric and Hybrid Vehicles

    Directory of Open Access Journals (Sweden)

    Ming Cheng

    2015-09-01

    Full Text Available The paper presents a number of advanced solutions on electric machines and machine-based systems for the powertrain of electric vehicles (EVs. Two types of systems are considered, namely the drive systems designated to the EV propulsion and the power split devices utilized in the popular series-parallel hybrid electric vehicle architecture. After reviewing the main requirements for the electric drive systems, the paper illustrates advanced electric machine topologies, including a stator permanent magnet (stator-PM motor, a hybrid-excitation motor, a flux memory motor and a redundant motor structure. Then, it illustrates advanced electric drive systems, such as the magnetic-geared in-wheel drive and the integrated starter generator (ISG. Finally, three machine-based implementations of the power split devices are expounded, built up around the dual-rotor PM machine, the dual-stator PM brushless machine and the magnetic-geared dual-rotor machine. As a conclusion, the development trends in the field of electric machines and machine-based systems for EVs are summarized.

  5. Advanced Tokamak Regimes in Alcator C-Mod with Lower Hybrid Current Drive

    Science.gov (United States)

    Parker, R.; Bonoli, P.; Gwinn, D.; Hutchinson, I.; Porkolab, M.; Ramos, J.; Bernabei, S.; Hosea, J.; Wilson, R.

    1999-11-01

    Alcator C-Mod has been proposed as a test-bed for developing advanced tokamak scenarios owing to its strong shaping, relatively long pulse length capability at moderate field, e.g. t ~ L/R at B = 5T and T_eo ~ 7keV, and the availability of strong ICRF heating. We plan to exploit this capability by installing up to 4 MW RF power at 4.6 GHz for efficient off-axis current drive by lower hybrid waves. By launching LH waves with a grill whose n_xx spectrum can be dynamically controlled over the range 2 2. Such reversed or nearly zero shear regimes have already been proposed as the basis of an advanced tokamak burning-plasma experiment-ATBX (M. Porkolab et al, IAEA-CN-69/FTP/13, IAEA,Yokohama 1998.), and could provide the basis for a demonstration power reactor. Theoretical and experimental basis for this advanced tokamak research program on C-Mod, including design of the lower hybrid coupler, its spectrum and current drive capabilities will be presented.

  6. Simulation of nuclear power plant dynamics with hybrid computer

    International Nuclear Information System (INIS)

    Results of simulation studies of the direct digital system of temperature control of the A-1 power plant reactor, carried out on a hybrid computer, are presented. The algorithm of such a control was programmed for the RPP 16 control computer as a user's code. A set of algorithms for studies of the sensitivity of dynamic system models to parameter changes and for the synthesis of multivariable decoupled control systems were compiled and programmed for a digital computer. Xenon oscillations in the core of the WWER type reactor were investigated using the D-decomposition technique. (author)

  7. IMPULSE---an advanced, high performance nuclear thermal propulsion system

    International Nuclear Information System (INIS)

    IMPULSE is an advanced nuclear propulsion engine for future space missions based on a novel conical fuel. Fuel assemblies are formed by stacking a series of truncated (U, Zr)C cones with non-fueled lips. Hydrogen flows radially inward between the cones to a central plenum connected to a high performance bell nozzle. The reference IMPULSE engine rated at 75,000 lb thrust and 1800 MWt weighs 1360 kg and is 3.65 meters in height and 81 cm in diameter. Specific impulse is estimated to be 1000 for a 15 minute life at full power. If longer life times are required, the operating temperature can be reduced with a concomitant decrease in specific impulse. Advantages of this concept include: well defined coolant paths without outlet flow restrictions; redundant orificing; very low thermal gradients and hence, thermal stresses, across the fuel elements; and reduced thermal stresses because of the truncated conical shape of the fuel elements

  8. Advanced interaction media in nuclear power plant control rooms.

    Science.gov (United States)

    Stephane, Lucas

    2012-01-01

    The shift from analog to digital Instruments (related mainly to information visualization) and Controls in Nuclear Power Plant Main Control Rooms (NPP MCR) is a central current topic of investigation. In NPP MCR, digitalization was implemented gradually, analog and digital systems still coexisting for the two main systems related to safety--Safety Instruments and Control System (SICS) and Process Instruments and Controls System (PICS). My ongoing research focuses on the introduction of Advanced Interaction Media (AIM) such as stereoscopic 3D visualization and multi-touch surfaces in control rooms. This paper proposes a Safety-Centric approach for gathering the Design Rationale needed in the specification of such novel AIM concepts as well as their evaluation through user tests. Beyond methodological research, the final output of the current research is to build an experimental simulator aiming to enhance improvements in Human-Systems Integration (HSI). This paper provides an overview of the topics under consideration. PMID:22317419

  9. Advanced computer graphics techniques as applied to the nuclear industry

    International Nuclear Information System (INIS)

    Computer graphics is a rapidly advancing technological area in computer science. This is being motivated by increased hardware capability coupled with reduced hardware costs. This paper will cover six topics in computer graphics, with examples forecasting how each of these capabilities could be used in the nuclear industry. These topics are: (1) Image Realism with Surfaces and Transparency; (2) Computer Graphics Motion; (3) Graphics Resolution Issues and Examples; (4) Iconic Interaction; (5) Graphic Workstations; and (6) Data Fusion - illustrating data coming from numerous sources, for display through high dimensional, greater than 3-D, graphics. All topics will be discussed using extensive examples with slides, video tapes, and movies. Illustrations have been omitted from the paper due to the complexity of color reproduction. 11 refs., 2 figs., 3 tabs

  10. UF6 cylinder washing at ANF [Advanced Nuclear Fuels

    International Nuclear Information System (INIS)

    Advanced Nuclear Fuels (ANF) Corporation receives UF6 cylinders in its Richland, WA fuel fabrication plant from its utility customers. Following transfer of the UF6, designated cylinders are cleaned by washing using a specialized process which emphasizes personnel safety and low cost. The cleaning operation is conducted in accordance with the guidelines is conducted in accordance with the guidelines of ANSI Standard N14.1. Specialized equipment has been developed for carrying out this operation with a minimum of space and manpower. Equipment designs and process methods are selected to ensure that the cylinders meet cleanliness requirements while maintaining low personnel radiation exposures, avoiding introduction of organic material and achieving low applied labor. A photo tour is used to illustrate the equipment and methods used

  11. Advancing nuclear technology and research. The advanced test reactor national scientific user facility

    International Nuclear Information System (INIS)

    The Advanced Test Reactor (ATR), at the Idaho National Laboratory (INL), is one of the world's premier test reactors for providing the capability for studying the effects of intense neutron and gamma radiation on reactor materials and fuels. The INL also has several hot cells and other laboratories in which irradiated material can be examined to study material radiation effects. In 2007 the US Department of Energy (DOE) designated the ATR as a National Scientific User Facility (NSUF) to facilitate greater access to the ATR and the associated INL laboratories for material testing research. The mission of the ATR NSUF is to provide access to world-class facilities, thereby facilitating the advancement of nuclear science and technology. Cost free access to the ATR, INL post irradiation examination facilities, and partner facilities is granted based on technical merit to U.S. university-led experiment teams conducting non-proprietary research. Proposals are selected via independent technical peer review and relevance to United States Department of Energy. To increase overall research capability, ATR NSUF seeks to form strategic partnerships with university facilities that add significant nuclear research capability to the ATR NSUF and are accessible to all ATR NSUF users. (author)

  12. Nuclear Hybrid Energy Systems - Regional Studies. West Texas and Northeastern Arizona

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, Humberto E. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Chen, Jun [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kim, Jong S. [Idaho National Lab. (INL), Idaho Falls, ID (United States); McKellar, Michael G. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Deason, Wesley R. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Vilim, Richard B. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bragg-Sitton, Shannon M. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Boardman, Richard D. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-04-01

    The primary objective of this study is to conduct a preliminary dynamic analysis of two realistic hybrid energy systems (HES) including a nuclear reactor as the main baseload heat generator (denoted as nuclear HES or nuclear hybrid energy systems [NHES]) and to assess the local (e.g., HES owners) and system (e.g., the electric grid) benefits attainable by the application of NHES in scenarios with multiple commodity production and high penetration of renewable energy. It is performed for regional cases - not generic examples - based on available resources, existing infrastructure, and markets within the selected regions. This study also briefly addresses the computational capabilities developed to conduct such analyses, reviews technical gaps, and suggests some research paths forward.

  13. Construction and engineering report for advanced nuclear fuel development facility

    International Nuclear Information System (INIS)

    The design and construction of the fuel technology development facility was aimed to accommodate general nuclear fuel research and development for the HANARO fuel fabrication and advanced fuel researches. 1. Building size and room function 1) Building total area : approx. 3,618m2, basement 1st floor, ground 3th floor 2) Room function : basement floor(machine room, electrical room, radioactive waste tank room), 1st floor(research reactor fuel fabrication facility, pyroprocess lab., metal fuel lab., nondestructive lab., pellet processing lab., access control room, sintering lab., etc), 2nd floor(thermal properties measurement lab., pellet characterization lab., powder analysis lab., microstructure analysis lab., etc), 3rd floor(AHU and ACU Room) 2. Special facility equipment 1) Environmental pollution protection equipment : ACU(2sets), 2) Emergency operating system : diesel generator(1set), 3) Nuclear material handle, storage and transport system : overhead crane(3sets), monorail hoist(1set), jib crane(2sets), tank(1set) 4) Air conditioning unit facility : AHU(3sets), packaged air conditioning unit(5sets), 5) Automatic control system and fire protection system : central control equipment(1set), lon device(1set), fire hose cabinet(3sets), fire pump(3sets) etc

  14. Construction and engineering report for advanced nuclear fuel development facility

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-09-01

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

  15. Feasibility study of advanced fuel burning nuclear reactors

    International Nuclear Information System (INIS)

    An investigation has been conducted to determine both physics, engineering and economic aspects of fusion power reactors based on magnetic confinement and on burning advanced fuels (AFs). DT burning Tokamaks are taken as reference concept. We show that the attractive features of advanced fuels, in particular of neutronlean proton-based AFs, can be combined, in appropriately designed AF reactors (high beta), with power densities comparable to or even higher than those achievable in DT Tokamaks. Moreover we identify physical requirements which would assure Q values well above unity. As an example a semi-open confinement scheme is analyzed based on a self-consistent plasma calculation. We find that a mirror, even if only ''semi-open'' as a result of strong diamagnetism, can barely be expected to achieve high Q values. Therefore confinement schemes such as compact tori, multipole surmacs etc. may be required to burn AFs. We conclude that the economics of AF reactors, as determined by the nuclear boiler power density, may be superior to that of DT-rectors if low recirculating power fractions can be obtained by appropriate plasma tayloring (high fractional transfer of fusion power to ions required). A more detailed investigation is suggested for proton-based fuel cycles. (orig.)

  16. Design related aspects in advanced nuclear fission plants

    International Nuclear Information System (INIS)

    Important issues to be considered for design of future reactors are: extrapolation of stress rupture data, creep-fatigue, negligible creep, damage monitoring. The paper highlights some new developments taking examples from a martensitic steel (mod 9% Cr), oxide dispersion strengthened (ODS) steels and nickel-base superalloys. Traditional approaches to extrapolation of (thermal) stress rupture data like Larson-Miller Parameter or Monkman-Grant rule seem to be valid concepts also for advanced reactors. However, a significant influence of cyclic softening on creep rates and stress rupture data can be expected as shown for grade 91. This is particularly true for creep-fatigue interactions. Based on cyclic stress-strain behaviour it is also possible to get very good life-time predictions under creep-fatigue with a strain range separation (inelastic fatigue and creep ranges) technique which could replace the currently used linear life fraction rule. Results from in-beam irradiation creep reveal no significant influence of dispersoid size. It can be assumed that irradiation creep is a matrix property. Finally it is shown that micro-sample testing of exposed material could be used as an advanced method for damage assessment in future nuclear power plants.

  17. An advanced aqueous process for nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    To develop an advanced aqueous reprocessing process using a minimal organic solvent and compact equipment to separate U, Pu and long-lived minor actinides from spent nuclear fuels, we have developed a new type of anion exchanger (AR-01) and several novel extraction resins containing a chelating ligand such as CMPO, Cyanex-301 and R-BTP. A hot separation experiment for a spent BWR-fuel solution was carried out by an ion exchange column packed with AR-01. To enhance the separation factor between U and FPs, electrolytic reduction of UO22+ to U+4 was studied using a flow type electrolysis cell with carbon-fiber electrode. Separation behavior of Am(III) from simulated HLW by CMPO and R-BTP impregnated resins were investigated. On the basis of the experimental results, an advanced aqueous process which consists of anion exchange as main separation method, electrolytic reduction for reducing U(VI) to U(IV) and extraction chromatography for MA partitioning has been designed and evaluated preliminarily. (author)

  18. Design related aspects in advanced nuclear fission plants

    International Nuclear Information System (INIS)

    The construction of nuclear power plants needs design codes (e.g. ASME or RCC-MR) to allow save and reliable design and operation. To meet the requirements of advanced future plants either existing codes have to be amended or new codes have to be developed. Future Generation IV plants like the very high temperature reactor (VHTR) or the sodium fast reactor (SFR) are currently in this stage of code development. Some important issues to be considered in this context are: design curves (lower bound scatter bands), creep-fatigue, negligible creep, crack growth (fatigue, creep, fast fracture), damage monitoring. The paper will provide some insight into the materials problems behind design rules. Examples will be taken from a martensitic steel (mod 9% Cr), oxide dispersion strengthened (ODS) steels and nickel-base superalloys. Possibilities for the replacement of the linear life fraction rule with advanced creep-fatigue damage assessments will be discussed. Specific emphasize will be put on the role of cyclic softening. Damage assessment and propagation of cracks from flaws under creep and fatigue will be touched upon. Some results from creep at low temperatures (irradiation creep, negligible creep) will be presented. (author)

  19. Recent advances in radiation monitoring systems for nuclear power stations

    International Nuclear Information System (INIS)

    Present projections indicate that by 1990 a minimum of 700 nuclear power stations will be in operation in at least 42 different countries. The health physics' profession is confronted, therefore, with a massive effort to control the radiological consequences of these operations. Regulations have been adopted or are being considered by the various governments to guide the health physicist. It is apparent that the necessary radiological measurements will become increasingly complex, require improved sensitivity and accuracy, increase in frequency, and demand more attention from the health physics staff. Computerized systems offer a cost-effective solution to keep these expanding requirements within manageable limits. The technology of computers, minicomputers and microcomputers is one of the most dynamic developments occurring in today's society. It has a history of doing 'more-for-less' as each new advancement reaches the commercial market. In the face of constant cost escalation in nuclear plant construction, the opportunity to provide more-for-less is a most welcome change. In anticipation of expanded radiological requirements and the availability of a compatible technology to meet them, the next step is to design and test a total system to be responsive to regulatory guidelines. Such a system will be described with appropriate emphases on both the data acquisition and data management subsystems. As the system evolves, it is logical to view its full purpose as a health physics operations center more than just another monitoring tool. Here the data vital to the decision-making processes are displayed rapidly and intelligently for interpretation by the operators. Overall, system design and operation should provide the health physicist with credible data to reflect favorably on the environmental and public acceptability of nuclear power

  20. Nuclear-Renewable Hybrid System Economic Basis for Electricity, Fuel, and Hydrogen

    Energy Technology Data Exchange (ETDEWEB)

    Charles Forsberg; Steven Aumeier

    2014-04-01

    Concerns about climate change and altering the ocean chemistry are likely to limit the use of fossil fuels. That implies a transition to a low-carbon nuclear-renewable electricity grid. Historically variable electricity demand was met using fossil plants with low capital costs, high operating costs, and substantial greenhouse gas emissions. However, the most easily scalable very-low-emissions generating options, nuclear and non-dispatchable renewables (solar and wind), are capital-intensive technologies with low operating costs that should operate at full capacities to minimize costs. No combination of fully-utilized nuclear and renewables can meet the variable electricity demand. This implies large quantities of expensive excess generating capacity much of the time. In a free market this results in near-zero electricity prices at times of high nuclear renewables output and low electricity demand with electricity revenue collapse. Capital deployment efficiency—the economic benefit derived from energy systems capital investment at a societal level—strongly favors high utilization of these capital-intensive systems, especially if low-carbon nuclear renewables are to replace fossil fuels. Hybrid energy systems are one option for better utilization of these systems that consumes excess energy at times of low prices to make some useful product.The economic basis for development of hybrid energy systems is described for a low-carbon nuclear renewable world where much of the time there are massivequantities of excess energy available from the electric sector.Examples include (1) high-temperature electrolysis to generate hydrogen for non-fossil liquid fuels, direct use as a transport fuel, metal reduction, etc. and (2) biorefineries.Nuclear energy with its concentrated constant heat output may become the enabling technology for economically-viable low-carbon electricity grids because hybrid nuclear systems may provide an economic way to produce dispatachable variable

  1. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume VIII. Advanced concepts

    International Nuclear Information System (INIS)

    The six advanced concepts for nuclear power systems that were selected for evaluation are: the fast mixed-spectrum reactor; the denatured molten-salt reactor; the mixed-flow gaseous-core reactor; the linear-accelerator fuel-regenerator reactor; the ternary metal-fueled electronuclear fuel-producer reactor; and the tokamak fusion-fission hybrid reactor. The design assessment was performed by identifying needs in six specific areas: conceptual plant design; reactor-physics considerations; fuel cycle alternatives; mechanical and thermal-hydraulic considerations; selection, development, and availability of materials; and engineering and operability. While none of the six concepts appears to be a credible commercial alternative to the liquid-metal fast-breeder within the Nonproliferation Alternative Systems Assessment Program horizon of 2025, there are a number of reasons for continued interest in the fast mixed-spectrum reactor: it is a once-through cycle fast reactor with proliferation risk characteristics similar to those of the light-water reactor; only about one-third as much uranium is required as for the once-through light-water reactor; the system will benefit directly from fast-breeder development programs; and, finally, the research and development required to develop the high-burnup metal fuel could benefit the on-going liquid-metal fast-breeder reactor program. Accordingly, a limited research and development effort on the high-burnup fuel seems justified, at present

  2. Advanced Power Conversion Efficiency in Inventive Plasma for Hybrid Toroidal Reactor

    Science.gov (United States)

    Hançerlioğullari, Aybaba; Cini, Mesut; Güdal, Murat

    2013-08-01

    Apex hybrid reactor has a good potential to utilize uranium and thorium fuels in the future. This toroidal reactor is a type of system that facilitates the occurrence of the nuclear fusion and fission events together. The most important feature of hybrid reactor is that the first wall surrounding the plasma is liquid. The advantages of utilizing a liquid wall are high power density capacity good power transformation productivity, the magnitude of the reactor's operational duration, low failure percentage, short maintenance time and the inclusion of the system's simple technology and material. The analysis has been made using the MCNP Monte Carlo code and ENDF/B-V-VI nuclear data. Around the fusion chamber, molten salts Flibe (LI2BeF4), lead-lithium (PbLi), Li-Sn, thin-lityum (Li20Sn80) have used as cooling materials. APEX reactor has modeled in the torus form by adding nuclear materials of low significance in the specified percentages between 0 and 12 % to the molten salts. In this study, the neutronic performance of the APEX fusion reactor using various molten salts has been investigated. The nuclear parameters of Apex reactor has been searched for Flibe (LI2BeF4) and Li-Sn, for blanket layers. In case of usage of the Flibe (LI2BeF4), PbLi, and thin-lityum (Li20Sn80) salt solutions at APEX toroidal reactors, fissile material production per source neutron, tritium production speed, total fission rate, energy reproduction factor has been calculated, the results obtained for both salt solutions are compared.

  3. Use of hybrid model in safety analyses of WWER-type nuclear power plants

    International Nuclear Information System (INIS)

    The development is described of hybrid model SIMOD developed jointly by the UVZU and ZES units of the Skoda Plzen enterprise for safety analyses of failure modes of WWER type nuclear power plant operation. A simple block diagram illustrates the analog and digital simulation of the individual circuits and components of the nuclear power unit and their interaction in relation to the control and protection system of the reactor and the unit. Simulated selected failure states of the nuclear power unit became the basis for processing safety documentation for the V-2 and Dukovany nuclear power plants with WWER-440 reactors. Methods are indicated for the verification of the computer program and its possible standardization. The basic trends are outlined in the development of the model for safety analyses of nuclear power units with WWER-1000 reactors. (author)

  4. Intercurrent fault diagnosis of nuclear power plants based on hybrid artificial neural network

    International Nuclear Information System (INIS)

    Based on the analysis of the structure of ART-2 and parallel BP neural network, a hybrid artificial neural network is proposed aiming at the intercurrent faults diagnosis of nuclear power plants. Firstly the ART-2 net is used to identify the single fault, then the parallel BP net is used to distinguish intercurrent faults from new fault. The simulation shows that, the hybrid artificial neural network resolves the problem of single neural network in distinguishing intercurrent faults from new fault, and can diagnose the intercurrent fault and new fault efficiently. (authors)

  5. Decontamination and Decommissioned Small Nuclear AIP Hybrid Systems Submarines

    OpenAIRE

    Guangya Liu; Daping Qiu

    2013-01-01

    Being equipped with small reactor AIP is the trend of conventional submarine power in 21st century as well as a real power revolution in conventional submarine. Thus, the quantity of small reactor AIP Submarines is on the increase, and its decommissioning and decontamination will also become a significant international issue. However, decommissioning the small reactor AIP submarines is not only a problem that appears beyond the lifetime of the small reactor nuclear devices, but the probl...

  6. Associations between cytoplasmic and nuclear Loci in hybridizing populations.

    OpenAIRE

    Orive, Maria E.; Barton, Nicholas H.

    2002-01-01

    We extend current multilocus models to describe the effects of migration, recombination, selection, and nonrandom mating on sets of genes in diploids with varied modes of inheritance, allowing us to consider the patterns of nuclear and cytonuclear associations (disequilibria) under various models of migration. We show the relationship between the multilocus notation recently presented by Kirkpatrick, Johnson, and Barton (developed from previous work by Barton and Turelli) and the cytonuclear ...

  7. Development of expert evaluation system for advanced nuclear power stations

    International Nuclear Information System (INIS)

    The wheels of the nuclear power industry in China are going to roll on the fast rails soon: It is important to establish an expert evaluation system for optimally selecting new types of NPPs in the future based on scientific evaluation. Under such a background, an expert evaluation system is developed to evaluate Various types of NPPs for the following two decades by taking into account the advices of selected top specialists in Chinese nuclear power industry, and by adopting different evaluation methods. The evaluation system is designed to use the database-MS-SQL Server or Oracle for manipulating experts' knowledge and objective data for scaling NPPs by user-selected evaluation methods for evaluating NPPs. The system includes two subsystems: one is called the Data Management Module and the other called the Evaluation Arithmetic Module. The Data Management Module is used to manage expert knowledge in forms of item marks of the NPPs given by experts of nuclear engineering. The Evaluation Arithmetic Module is used to analyze and deal with the evaluation based on the data in the Database by certain designed evaluation method, and to provide the evaluation results. Based on the users' selection, the evaluation of the NPPs is processed, and the results can be dynamically listed in table or displayed in graphics. So it can be used as a consulting tool to help users make optimal selection of prospective NPPs. The system is developed in architecture of the mixture framework C/S(Client/Server) and B/S(Browse/Server), thus is safe, advanced, extensible and user- friendly. The present system is computer network based, so it can be used not only in personal PC and local network, but also in the Web Server which can be browsed by remote users. To develop such an evaluation system is an initiative R and D project in Chinese nuclear R and D activities. Although the evaluation system is far from perfect, however, the preliminary evaluation results produced by the evaluation

  8. DEMONSTRATION OF A FULL-SCALE RETROFIT OF THE ADVANCED HYBRID PARTICULATE COLLECTOR TECHNOLOGY

    Energy Technology Data Exchange (ETDEWEB)

    Tom Hrdlicka; William Swanson

    2005-12-01

    The Advanced Hybrid Particulate Collector (AHPC), developed in cooperation between W.L. Gore & Associates and the Energy & Environmental Research Center (EERC), is an innovative approach to removing particulates from power plant flue gas. The AHPC combines the elements of a traditional baghouse and electrostatic precipitator (ESP) into one device to achieve increased particulate collection efficiency. As part of the Power Plant Improvement Initiative (PPII), this project was demonstrated under joint sponsorship from the U.S. Department of Energy and Otter Tail Power Company. The EERC is the patent holder for the technology, and W.L. Gore & Associates was the exclusive licensee for this project. The project objective was to demonstrate the improved particulate collection efficiency obtained by a full-scale retrofit of the AHPC to an existing electrostatic precipitator. The full-scale retrofit was installed on an electric power plant burning Powder River Basin (PRB) coal, Otter Tail Power Company's Big Stone Plant, in Big Stone City, South Dakota. The $13.4 million project was installed in October 2002. Project related testing concluded in December 2005. The following Final Technical Report has been prepared for the project entitled ''Demonstration of a Full-Scale Retrofit of the Advanced Hybrid Particulate Collector Technology'' as described in DOE Award No. DE-FC26-02NT41420. The report presents the operation and performance results of the system.

  9. Solid state nuclear magnetic resonance investigations of advanced energy materials

    Science.gov (United States)

    Bennett, George D.

    In order to better understand the physical electrochemical changes that take place in lithium ion batteries and asymmetric hybrid supercapacitors solid state nuclear magnetic resonance (NMR) spectroscopy has been useful to probe and identify changes on the atomic and molecular level. NMR is used to characterize the local environment and investigate the dynamical properties of materials used in electrochemical storage devices (ESD). NMR investigations was used to better understand the chemical composition of the solid electrolyte interphase which form on the negative and positive electrodes of lithium batteries as well as identify the breakdown products that occur in the operation of the asymmetric hybrid supercapacitors. The use of nano-structured particles in the development of new materials causes changes in the electrical, structural and other material properties. NMR was used to investigate the affects of fluorinated and non fluorinated single wall nanotubes (SWNT). In this thesis three experiments were performed using solid state NMR samples to better characterize them. The electrochemical reactions of a lithium ion battery determine its operational profile. Numerous means have been employed to enhance battery cycle life and operating temperature range. One primary means is the choice and makeup of the electrolyte. This study focuses on the characteristics of the solid electrolyte interphase (SEI) that is formed on the electrodes surface during the charge discharge cycle. The electrolyte in this study was altered with several additives in order to determine the influence of the additives on SEI formation as well as the intercalation and de-intercalation of lithium ions in the electrodes. 7Li NMR studies where used to characterize the SEI and its composition. Solid state NMR studies of the carbon enriched acetonitrile electrolyte in a nonaqueous asymmetric hybrid supercapacitor were performed. Magic angle spinning (MAS) coupled with cross polarization NMR

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

    International Nuclear Information System (INIS)

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

  11. Decontamination and Decommissioned Small Nuclear AIP Hybrid Systems Submarines

    Directory of Open Access Journals (Sweden)

    Guangya Liu

    2013-11-01

    Full Text Available Being equipped with small reactor AIP is the trend of conventional submarine power in 21st century as well as a real power revolution in conventional submarine. Thus, the quantity of small reactor AIP Submarines is on the increase, and its decommissioning and decontamination will also become a significant international issue. However, decommissioning the small reactor AIP submarines is not only a problem that appears beyond the lifetime of the small reactor nuclear devices, but the problem involving the entire process of design, construction, running and closure. In the paper, the problem is explored based on the conception and the feasible decommissioning and decontamination means are supplied to choose from.

  12. Reactor Subsystem Simulation for Nuclear Hybrid Energy Systems

    Energy Technology Data Exchange (ETDEWEB)

    Shannon Bragg-Sitton; J. Michael Doster; Alan Rominger

    2012-09-01

    Preliminary system models have been developed by Idaho National Laboratory researchers and are currently being enhanced to assess integrated system performance given multiple sources (e.g., nuclear + wind) and multiple applications (i.e., electricity + process heat). Initial efforts to integrate a Fortran-based simulation of a small modular reactor (SMR) with the balance of plant model have been completed in FY12. This initial effort takes advantage of an existing SMR model developed at North Carolina State University to provide initial integrated system simulation for a relatively low cost. The SMR subsystem simulation details are discussed in this report.

  13. Advanced energy system with nuclear reactors as an energy source

    International Nuclear Information System (INIS)

    recovery system is also applicable to a fast reactor (FR) with a supercritical CO2 gas turbine that achieves higher cycle efficiency than conventional sodium cooled FRs with steam turbines. The FR will eliminate problems of conventional FRs related to safety, plant maintenance, and construction costs. The FR consumes efficiently trans-uranium elements (TRU) produced in light water reactors as fuel and reduce long-lived radioactive wastes or environmental loads of long term geological disposal. An Advanced Energy System (AES) with nuclear reactors as an energy source has been proposed which supply electricity and heat to cities. The AES has three objectives: 1. Save energy resources and reduce green house gas emissions, attaining total energy utilization efficiency higher than 85% through waste heat recovery and utilization. 2. Foster a recycling society that produces methane and methanol for fuel cells from waste products of cities and farms. 3. Consume TRU produced in LWRs as fuel for FRs, and reduce long-lived radioactive wastes or environmental loads of long term geological disposal. References 1. Y. Kato, T. Nitawaki and K. Fujima, 'Zero Waste Heat Release Nuclear Cogeneration System, 'Proc. 2003 Intl. Congress on Advanced Nuclear Power Plants (ICAPP'03), Cordoba, Spain, May 4-7, 2003, Paper 3313. 2. Y. Kato, T. Nitawaki and Y. Muto, 'Medium Temperature Carbon Dioxide Gas Turbine Reactor, 'Nucl. Eng. Design, 230, pp. 195-207 (2004). 3. H. N. Tran and Y. Kato, 'New 237Np Burning Strategy in a Supercritical CO2 Cooled Fast Reactor Core Attaining Zero Burnup Reactivity Loss,' Proc. American Nuclear Society's Topical Meeting on Reactor Physics (PHYSOR 2006), Vancouver, British Columbia, Canada, September 10-14, 2006

  14. Advanced nuclear fuel for VVER reactors. Status and operation experience

    International Nuclear Information System (INIS)

    The paper discusses the major VVER fuel trends, aimed at the enhancement of FAs' effectiveness and reliability, flexibility of their operating performances and fuel cycle efficiency, specifically: (i) Fuel burnup increasing is one of the major objectives during the development of improved nuclear fuel and fuel cycles. At present, the achieved fuel rod burn up is 65 MWdays/kgU. The tasks are set and the activities are carried out to achieve fuel rod burnup up to 70 MWdays/kgU and burnup of discharged batch of FAs - up to 60 MWdays/kgU. (ii) Improvement of FA rigidity enables to increase operating reliability of fuel due to gaps reducing between FAs and, as a result, the fall of peak load coefficients. FA geometric stability enables to optimize the speed of handling procedures with fuel. (iii) Increasing of uranium content of FA is aimed at extension of fuel cycles' duration. Fuel weight increase in FA is achieved both due to fuel column height extension and to changes of pellet geometrical size. (iv) Extension of FA service live satisfies the up-to-date NPP requirements for fuel cycles of various duration from 4x320 eff. days to 5x320 eff. days and 3x480 eff. days. (v) The development of new-generation FAs with increased strength characteristics has required the zirconium alloys' improvement. Advanced zirconium alloys shall provide safety and effectiveness of FA and fuel rods during long-life operation up to 40 000 eff. hours. (vi) Utilization of reprocessed uranium enables to use spent nuclear fuel in cycle and to create the partly complete fuel cycle for VVER reactors. This paper summarizes the major operating results of LTAs, which meet the modern and prospective requirements for VVER fuel, at Russian NPPs with VVER-440 and VVER-1000 reactors. (author)

  15. IDENTIFICATION OF PUTATIVE HYBRIDS AND NATURAL LINEAGES IN GENUS POTAMOGETON REVEALED BY CHLOROPLAST AND NUCLEAR DNA MARKERS

    Directory of Open Access Journals (Sweden)

    Tao Zhang

    2012-06-01

    Full Text Available Phylogenetic relations of hybrids and non-hybrid species in the genus Potamogeton were reconstructed based on three spacers and one intron of chloroplast sequences and nuclear sequences of 5S-NTS. By comparing the phylogenetic relationships of subgenus Potamogeton with floral size, we propose that the split in the two main lineages reflects an early differentiation of flower size, perhaps due to the shift from out- to in-breeding; we also presume that more complex evolutionary processes exist in subgenus Potamogeton based on present study. As natural hybridization plays a fundamental role in the evolution of Potamogeton, frequently resulting in the formation of entirely new species, compelling evidence supports the hybrid origin of species: P. anguillanus, P. hubeiensis, P. kamogawaensis, and the triple hybrid-P. sp. hybrid. Incongruence between nuclear and plastid tree indicated that introgression might had occurred from subgenus Coleogeton to subgenus Potamogeton

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

    International Nuclear Information System (INIS)

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

  17. Advanced Nuclear Fuel Cycle Transitions: Optimization, Modeling Choices, and Disruptions

    Science.gov (United States)

    Carlsen, Robert W.

    Many nuclear fuel cycle simulators have evolved over time to help understan the nuclear industry/ecosystem at a macroscopic level. Cyclus is one of th first fuel cycle simulators to accommodate larger-scale analysis with it liberal open-source licensing and first-class Linux support. Cyclus also ha features that uniquely enable investigating the effects of modeling choices o fuel cycle simulators and scenarios. This work is divided into thre experiments focusing on optimization, effects of modeling choices, and fue cycle uncertainty. Effective optimization techniques are developed for automatically determinin desirable facility deployment schedules with Cyclus. A novel method fo mapping optimization variables to deployment schedules is developed. Thi allows relationships between reactor types and scenario constraints to b represented implicitly in the variable definitions enabling the usage o optimizers lacking constraint support. It also prevents wasting computationa resources evaluating infeasible deployment schedules. Deployed power capacit over time and deployment of non-reactor facilities are also included a optimization variables There are many fuel cycle simulators built with different combinations o modeling choices. Comparing results between them is often difficult. Cyclus flexibility allows comparing effects of many such modeling choices. Reacto refueling cycle synchronization and inter-facility competition among othe effects are compared in four cases each using combinations of fleet of individually modeled reactors with 1-month or 3-month time steps. There are noticeable differences in results for the different cases. The larges differences occur during periods of constrained reactor fuel availability This and similar work can help improve the quality of fuel cycle analysi generally There is significant uncertainty associated deploying new nuclear technologie such as time-frames for technology availability and the cost of buildin advanced reactors

  18. The Advanced Test Reactor National Scientific User Facility Advancing Nuclear Technology

    International Nuclear Information System (INIS)

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

  19. The advanced test reactor national scientific user facility advancing nuclear technology

    International Nuclear Information System (INIS)

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

  20. A hybrid approach to solving the problem of design of nuclear fuel cells

    International Nuclear Information System (INIS)

    An approach to solving the problem of fuel cell design for BWR power reactor is presented. For this purpose the hybridization of a method based in heuristic knowledge rules called S15 and the advantages of a meta-heuristic method is proposed. The synergy of potentialities of both techniques allows finding solutions of more quality. The quality of each solution is obtained through a multi-objective function formed from the main cell parameters that are provided or obtained during the simulation with the CASMO-4 code. To evaluate this alternative of solution nuclear fuel cells of reference of nuclear power plant of Laguna Verde were used. The results show that in a systematic way the results improve when both methods are coupled. As a result of the hybridization process of the mentioned techniques an improvement is achieved in a range of 2% with regard to the achieved results in an independent way by the S15 method. (Author)

  1. MorphologiCal and Cytogenetic Analysis on the Advanced Generations of Generic Hybrids between Brassica napus and Orychophragmus violaceu

    Institute of Scientific and Technical Information of China (English)

    Zhigang ZHAO; Dezhi DU; Zaiyun LI

    2012-01-01

    Objective This study aimed to reveal the genetic changes of advanced generation hybrids between Brassica napus and Orychophragmus violaceus. [Method] The morphological characteristics such as the plant shape, branching sites, leaf shape, leaf color, primary branches and secondary branches, as well as the cytolog- ical characteristics of the advanced generation hybrids (Fs-F10) between B. napus and O. violaceus were observed. [Result] The morphology analysis revealed that the hybrid progeny was more like B. rapa in leaf shape, leaf color, plant shape and ear- ly flowering phenotype, whereas more like B. napus in number of secondary branch- es, silique length and 1 000-seed weight. Analysis on the cytogenetics characteristics showed that these advanced inbred progenies were hypoploids with less than 38 chromosomes; moreover, all the chromosomes from O. violaceus had been lost. Chromosome pairings at meiotic diakinesis of hybrids between the advanced inbred progenies and B. rapa revealed that chromosomes lost in hypoploids possibly be- longed to the C genome of B. oleracea. With generations developing, chromosomes number of plants from two populations gradually increased and developed into the number of B. napus (2n=38). [Conclusion] This study will provide reference to reveal the source of chromosome lost in hypoploids and the morphological change of hybrids.

  2. Hybridization of natural systems with advanced treatment processes for organic micropollutant removals: New concepts in multi-barrier treatment

    KAUST Repository

    Sudhakaran, Sairam

    2013-07-01

    In the past, emphasis has been on individual treatment processes comprising conventional treatment (coagulation, sedimentation, and filtration) followed by advanced treatment processes (adsorption, ion-exchange, oxidation, and membrane separation). With the depletion of water resources and high demand for power and chemical usage, efforts need to be made to judiciously use advanced treatment processes. There is a new interest in multiple barriers with synergies in which two coupled processes can function as a hybrid process. Within the context of this paper, the hybrid processes include a natural treatment process coupled with an advanced process. Pilot/full-scale studies have shown efficient removal of OMPs by these hybrid processes. With this hybridization, the usage of resources such as power and chemicals can be reduced. In this study, coupling/hybridization of aquifer recharge and recovery (ARR) with oxidation (O3), advanced oxidation process which involves OH radicals (AOP), nanofiltration (NF), reverse osmosis (RO) and granular activated carbon (GAC) adsorption for OMP removal was studied. O3 or AOP as a pre-treatment and GAC, NF, RO, or UV/chlorination as a post-treatment to ARR was studied. NF can be replaced by RO for removal of OMPs since studies have shown similar performance of NF to RO for removal of many OMPs, thereby reducing costs and providing a more sustainable approach. © 2013 Elsevier Ltd.

  3. Hybridization of natural systems with advanced treatment processes for organic micropollutant removals: new concepts in multi-barrier treatment.

    Science.gov (United States)

    Sudhakaran, Sairam; Maeng, Sung Kyu; Amy, Gary

    2013-07-01

    Organic micropollutants (OMPs) represent a major constraint in drinking water supply. In the past, emphasis has been on individual treatment processes comprising conventional treatment (coagulation, sedimentation, and filtration) followed by advanced treatment processes (adsorption, ion-exchange, oxidation, and membrane separation). With the depletion of water resources and high demand for power and chemical usage, efforts need to be made to judiciously use advanced treatment processes. There is a new interest in multiple barriers with synergies in which two coupled processes can function as a hybrid process. Within the context of this paper, the hybrid processes include a natural treatment process coupled with an advanced process. Pilot/full-scale studies have shown efficient removal of OMPs by these hybrid processes. With this hybridization, the usage of resources such as power and chemicals can be reduced. In this study, coupling/hybridization of aquifer recharge and recovery (ARR) with oxidation (O3), advanced oxidation process which involves OH radicals (AOP), nanofiltration (NF), reverse osmosis (RO) and granular activated carbon (GAC) adsorption for OMP removal was studied. O3 or AOP as a pre-treatment and GAC, NF, RO, or UV/chlorination as a post-treatment to ARR was studied. NF can be replaced by RO for removal of OMPs since studies have shown similar performance of NF to RO for removal of many OMPs, thereby reducing costs and providing a more sustainable approach. PMID:23664475

  4. Advanced nuclear power options: The driving forces and their results

    International Nuclear Information System (INIS)

    Successful nuclear power plant concepts must simultaneously demonstrate satisfactory performance in terms of both safety and economics. In order to be attractive to both electric utility companies and the public, such plants must produce economical electric energy consistent with a level of safety which is acceptable to both the public and the plant owner. Programs for reactor development worldwide can be classified according to whether the reactor concept pursues improved safety or improved economic performance as the primary objective. When improved safety is the primary goal, safety enters the solution of the design problem as a constraint which restricts the set of allowed solutions. Conversely, when improved economic performance is the primary goal it is allowed to be pursued only to an extent which is compatible with stringent safety requirements. The three major reactor coolants under consideration for future advanced reactor use are water, helium and sodium. Reactor development programs focused upon safety and upon economics using each coolant are being pursued worldwide. It is seen that the safety-oriented concepts are typically of lower capacity by approximately an order of magnitude, than the economics-oriented concepts. This is the result, in the former concept, of using less efficient, but more reliable, means of accomplishing essential safety functions. (author)

  5. Advancement of safeguards inspection technology for CANDU nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jae Sung; Park, W. S.; Cha, H. R.; Ham, Y. S.; Lee, Y. G.; Kim, K. P.; Hong, Y. D

    1999-04-01

    The objectives of this project are to develop both inspection technology and safeguards instruments, related to CANDU safeguards inspection, through international cooperation, so that those outcomes are to be applied in field inspections of national safeguards. Furthermore, those could contribute to the improvement of verification correctness of IAEA inspections. Considering the level of national inspection technology, it looked not possible to perform national inspections without the joint use of containment and surveillance equipment conjunction with the IAEA. In this connection, basic studies for the successful implementation of national inspections was performed, optimal structure of safeguards inspection was attained, and advancement of safeguards inspection technology was forwarded. The successful implementation of this project contributed to both the improvement of inspection technology on CANDU reactors and the implementation of national inspection to be performed according to the legal framework. In addition, it would be an opportunity to improve the ability of negotiating in equal shares in relation to the IAEA on the occasion of discussing or negotiating the safeguards issues concerned. Now that the national safeguards technology for CANDU reactors was developed, the safeguards criteria, procedure and instruments as to the other item facilities and fabrication facilities should be developed for the perfection of national inspections. It would be desirable that the recommendations proposed and concreted in this study, so as to both cope with the strengthened international safeguards and detect the undeclared nuclear activities, could be applied to national safeguards scheme. (author)

  6. Advancement of safeguards inspection technology for CANDU nuclear power plants

    International Nuclear Information System (INIS)

    The objectives of this project are to develop both inspection technology and safeguards instruments, related to CANDU safeguards inspection, through international cooperation, so that those outcomes are to be applied in field inspections of national safeguards. Furthermore, those could contribute to the improvement of verification correctness of IAEA inspections. Considering the level of national inspection technology, it looked not possible to perform national inspections without the joint use of containment and surveillance equipment conjunction with the IAEA. In this connection, basic studies for the successful implementation of national inspections was performed, optimal structure of safeguards inspection was attained, and advancement of safeguards inspection technology was forwarded. The successful implementation of this project contributed to both the improvement of inspection technology on CANDU reactors and the implementation of national inspection to be performed according to the legal framework. In addition, it would be an opportunity to improve the ability of negotiating in equal shares in relation to the IAEA on the occasion of discussing or negotiating the safeguards issues concerned. Now that the national safeguards technology for CANDU reactors was developed, the safeguards criteria, procedure and instruments as to the other item facilities and fabrication facilities should be developed for the perfection of national inspections. It would be desirable that the recommendations proposed and concreted in this study, so as to both cope with the strengthened international safeguards and detect the undeclared nuclear activities, could be applied to national safeguards scheme. (author)

  7. Advanced surveillance of Resistance Temperature Detectors in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Highlights: • A two time constant transfer function is proposed to describe the Resistance Temperature Detector dynamics. • One constant is only related to the inner dynamics whereas the other one is related to the process and to the inner dynamics. • The two time constants have been found in several RTDs from a Nuclear Power Plant. • A Monte Carlo simulation is used to properly adjust the sampling time to find both constants. - Abstract: The dynamic response of several RTDs located at the cold leg of a PWR has been studied. A theoretical model for the heat transfer between the RTDs and the surrounding fluid is derived. It proposes a two real poles transfer function. By means of noise analysis techniques in the time domain (autoregressive models) and the Dynamic Data System methodology, the two time constants of the system can be found. A Monte Carlo simulation is performed in order to choose the proper sampling time to obtain both constants. The two poles are found and they permit an advance in situ surveillance of the sensor response time and the sensor dynamics performance. One of the poles is related to the inner dynamics whereas the other one is linked to the process and the inner dynamics. So surveillance on the process and on the inner dynamics can be distinguished

  8. An Advanced Tokamak Fusion Nuclear Science Facility (FNSF-AT)

    Science.gov (United States)

    Chan, V. S.; Garofalo, A. M.; Stambaugh, R. D.

    2010-11-01

    A Fusion Development Facility (FDF) is a candidate for FNSF-AT. It is a compact steady-state machine of moderate gain that uses AT physics to provide the neutron fluence required for fusion nuclear science development. FDF is conceived as a double-null plasma with high elongation and triangularity, predicted to allow good confinement of high plasma pressure. Steady-state is achieved with high bootstrap current and radio frequency current drive. Neutral beam injection and 3D non-resonant magnetic field can provide edge plasma rotation for stabilization of MHD and access to Quiescent H-mode. The estimated power exhaust is somewhat lower than that of ITER because of higher core radiation and stronger tilting of the divertor plates. FDF is capable of further developing all elements of AT physics, qualifying them for an advanced performance DEMO. The latest concept has accounted for realistic neutron shielding and divertor implementation. Self-consistent evolution of the transport profiles and equilibrium will quantify the stability and confinement required to meet the FNS mission.

  9. Advanced CANDU reactor technology: competitive design for the nuclear renaissance

    International Nuclear Information System (INIS)

    AECL has developed the design for a new generation of CANDU nuclear power plants, the Advance CANDU Reactor or ACR. The ACR combines a set of underlying enabling technologies with well-established successful CANDU features in an optimized design with significantly lower costs. By adopting slightly enriched uranium fuel, an optimized core design with light water coolant, heavy water moderator and reflector has been defined based on the existing CANDU fuel channel module. The basic design for the complete reference ACR power plant has now been completed. This paper summarizes the main features and characteristics of the reference ACR-700 power plant design. The progress of the ACR design program in meeting challenging cost, schedule and performance targets is described. AECL's cost reduction methodology is summarized as an integral part of the design optimization process. Examples are given of cost reduction features together with the enhancement of design margins. AECL expects the detailed design and testing of ACR to be complete and pre-project licensing evaluation carried out to enable regulatory endorsement in key markets by the middle of the decade. (authors)

  10. Advanced Test Reactor National Scientific User Facility: Addressing advanced nuclear materials research

    Energy Technology Data Exchange (ETDEWEB)

    John Jackson; Todd Allen; Frances Marshall; Jim Cole

    2013-03-01

    The Advanced Test Reactor National Scientific User Facility (ATR NSUF), based at the Idaho National Laboratory in the United States, is supporting Department of Energy and industry research efforts to ensure the properties of materials in light water reactors are well understood. The ATR NSUF is providing this support through three main efforts: establishing unique infrastructure necessary to conduct research on highly radioactive materials, conducting research in conjunction with industry partners on life extension relevant topics, and providing training courses to encourage more U.S. researchers to understand and address LWR materials issues. In 2010 and 2011, several advanced instruments with capability focused on resolving nuclear material performance issues through analysis on the micro (10-6 m) to atomic (10-10 m) scales were installed primarily at the Center for Advanced Energy Studies (CAES) in Idaho Falls, Idaho. These instruments included a local electrode atom probe (LEAP), a field-emission gun scanning transmission electron microscope (FEG-STEM), a focused ion beam (FIB) system, a Raman spectrometer, and an nanoindentor/atomic force microscope. Ongoing capability enhancements intended to support industry efforts include completion of two shielded, irradiation assisted stress corrosion cracking (IASCC) test loops, the first of which will come online in early calendar year 2013, a pressurized and controlled chemistry water loop for the ATR center flux trap, and a dedicated facility intended to house post irradiation examination equipment. In addition to capability enhancements at the main site in Idaho, the ATR NSUF also welcomed two new partner facilities in 2011 and two new partner facilities in 2012; the Oak Ridge National Laboratory, High Flux Isotope Reactor (HFIR) and associated hot cells and the University California Berkeley capabilities in irradiated materials analysis were added in 2011. In 2012, Purdue University’s Interaction of Materials

  11. Research and development on the application of advanced control technologies to advanced nuclear reactor systems: A US national perspective

    International Nuclear Information System (INIS)

    Control system designs for nuclear power plants are becoming more advanced through the use of digital technology and automation. This evolution is taking place because of: (1) the limitations in analog based control system performance and maintenance and availability and (2) the promise of significant improvement in plant operation and availability due to advances in digital and other control technologies. Digital retrofits of control systems in US nuclear plants are occurring now. Designs of control and protection systems for advanced LWRs are based on digital technology. The use of small inexpensive, fast, large-capacity computers in these designs is the first step of an evolutionary process described in this paper. Under the sponsorship of the US Department of Energy (DOE), Oak Ridge National Laboratory, Argonne National Laboratory, GE Nuclear Energy and several universities are performing research and development in the application of advances in control theory, software engineering, advanced computer architectures, artificial intelligence, and man-machine interface analysis to control system design. The target plant concept for the work described in this paper is the Power Reactor Inherently Safe Module reactor (PRISM), an advanced modular liquid metal reactor concept. This and other reactor designs which provide strong passive responses to operational upsets or accidents afford good opportunities to apply these advances in control technology. 18 refs., 5 figs

  12. NEPTUNE: A new software platform for advanced nuclear thermal hydraulics

    International Nuclear Information System (INIS)

    The NEPTUNE project constitutes the thermal-hydraulic part of the long-term Electricite de France and Commissariat a l'Energie Atomique joint research and development program for the next generation of nuclear reactor simulation tools. This program is also financially supported by the Institut de Radioprotection et Surete Nucleaire and AREVA NP. The project aims at developing a new software platform for advanced two-phase flow thermal hydraulics covering the whole range of modeling scales and allowing easy multi-scale and multidisciplinary calculations. NEPTUNE is a fully integrated project that covers the following fields: software development, research in physical modeling and numerical methods, development of advanced instrumentation techniques, and performance of new experimental programs. The analysis of the industrial needs points out that three main simulation scales are involved. The system scale is dedicated to the overall description of the reactor. The component or subchannel scale allows three-dimensional computations of the main components of the reactors: cores, steam generators, condensers, and heat exchangers. The current generation of system and component codes has reached a very high level of maturity for industrial applications. The third scale, computational fluid dynamics (CFD) in open medium, allows one to go beyond the limits of the component scale for a finer description of the flows. This scale opens promising perspectives for industrial simulations, and the development and validation of the NEPTUNE CFD module have been a priority since the beginning of the project. It is based on advanced physical models (two-fluid or multi field model combined with interfacial area transport and two-phase turbulence) and modern numerical methods (fully unstructured finite volume solvers). For the system and component scales, prototype developments have also started, including new physical models and numerical methods. In addition to scale

  13. High-speed and low-power silicon-organic hybrid modulators for advanced modulation formats

    Science.gov (United States)

    Lauermann, M.; Wolf, S.; Palmer, R.; Koeber, S.; Schindler, P. C.; Wahlbrink, T.; Bolten, J.; Giesecke, A. L.; Koenigsmann, M.; Kohler, M.; Malsam, D.; Elder, D. L.; Dalton, L. R.; Leuthold, J.; Freude, W.; Koos, C.

    2015-05-01

    We demonstrate silicon-organic hybrid (SOH) modulators for generating advanced modulation formats at high data rates and with low energy consumption. SOH integration combines slot waveguides on conventional silicon-on-insulator substrates with highly efficient electro-optic materials. With this approach we generate 16QAM signals at symbol rates of 28 GBd and 40 GBd leading to gross data rates (net data rates) of up to 160 Gbit/s (133 Gbit/s) for a single polarization. This is the highest value achieved by a silicon-based modulator up to now. With a maximum symbol rate of 28 GBd, low drive voltages of only 0.6 Vpp are sufficient and result in a record-low energy consumption of only 19 fJ/bit. This is the lowest energy consumption that has so far been reported for a 16QAM modulator at 28 GBd.

  14. Recent advances on multi-component hybrid nanostructures for electrochemical capacitors

    Science.gov (United States)

    Xiong, Pan; Zhu, Junwu; Wang, Xin

    2015-10-01

    With the continuously growing energy demand and ever-escalating environmental problems, the great energy transition from conventional fossil fuels to renewable sources of energy is under way, and requires more efficient and reliable electrochemical energy storage devices, such as electrochemical capacitors (also called as supercapacitors). In order to achieve high energy and power densities of supercapacitors, numerous efforts are devoted to the development of advanced multi-component hybrid electrode materials for realizing high-performance. This review summarizes the most recent progress in the development of nanostructured electrode materials for energy storage, with a particular focus on these nanostructures that integrate carbon materials, metal oxides/hydroxides and conducting polymers for enhancing energy storage performances via taking advantage of each component's unique functionality and their synergetic effects. Finally, we give some perspectives on the challenges and opportunities in this intriguing field.

  15. Advancing Plug-In Hybrid Technology and Flex Fuel Application on a Chrysler Minivan

    Energy Technology Data Exchange (ETDEWEB)

    Bazzi, Abdullah [Chrysler Group LLC, Auburn Hills, MI (United States); Barnhart, Steven [Chrysler Group LLC, Auburn Hills, MI (United States)

    2014-12-31

    FCA US LLC viewed this DOE funding as a historic opportunity to begin the process of achieving required economies of scale on technologies for electric vehicles. The funding supported FCA US LLC’s light-duty electric drive vehicle and charging infrastructure-testing activities and enabled FCA US LLC to utilize the funding on advancing Plug-in Hybrid Electric Vehicle (PHEV) technologies to future programs. FCA US LLC intended to develop the next generations of electric drive and energy batteries through a properly paced convergence of standards, technology, components, and common modules, as well as first-responder training and battery recycling. To support the development of a strong, commercially viable supplier base, FCA US LLC also used this opportunity to evaluate various designated component and sub-system suppliers. The original project proposal was submitted in December 2009 and selected in January 2010. The project ended in December 2014.

  16. BUTREN-RC an hybrid system for the recharges optimization of nuclear fuels in a BWR

    International Nuclear Information System (INIS)

    The obtained results with the hybrid system BUTREN-RC are presented that obtains recharges of nuclear fuel for a BWR type reactor. The system has implemented the methods of optimization heuristic taboo search and neural networks. The optimization it carried out with the technique of taboo search, and the neural networks, previously trained, were used to predict the behavior of the recharges of fuel, in substitution of commercial codes of reactor simulation. The obtained recharges of nuclear fuel correspond to 5 different operation cycles of the Laguna Verde Nuclear Power plant, Veracruz in Mexico. The obtained results were compared with the designs of this cycles. The energy gain with the recharges of fuel proposals is of approximately 4.5% with respect to those of design. The time of compute consumed it was considerably smaller that when a commercial code for reactor simulation is used. (Author)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  19. Proceedings of 2009 international congress on advances in nuclear power plants

    International Nuclear Information System (INIS)

    This CD-ROM is the collection of the paper presented at the 2009 International Congress on Advances in Nuclear Power Plants (ICAPP'09) . The 365 of the presented papers are indexed individually. (J.P.N.)

  20. Advanced Turbine Technology Applications Project (ATTAP) and Hybrid Vehicle Turbine Engine Technology Support project (HVTE-TS): Final summary report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-01

    This final technical report was prepared by Rolls-Royce Allison summarizing the multiyear activities of the Advanced Turbine Technology Applications Project (ATTAP) and the Hybrid Vehicle Turbine Engine Technology Support (HVTE-TS) project. The ATTAP program was initiated in October 1987 and continued through 1993 under sponsorship of the US Department of Energy (DOE), Energy Conservation and Renewable Energy, Office of Transportation Technologies, Propulsion Systems, Advanced Propulsion Division. ATTAP was intended to advance the technological readiness of the automotive ceramic gas turbine engine. The target application was the prime power unit coupled to conventional transmissions and powertrains. During the early 1990s, hybrid electric powered automotive propulsion systems became the focus of development and demonstration efforts by the US auto industry and the Department of energy. Thus in 1994, the original ATTAP technology focus was redirected to meet the needs of advanced gas turbine electric generator sets. As a result, the program was restructured to provide the required hybrid vehicle turbine engine technology support and the project renamed HVTE-TS. The overall objective of the combined ATTAP and HVTE-TS projects was to develop and demonstrate structural ceramic components that have the potential for competitive automotive engine life cycle cost and for operating 3,500 hr in an advanced high temperature turbine engine environment. This report describes materials characterization and ceramic component development, ceramic components, hot gasifier rig testing, test-bed engine testing, combustion development, insulation development, and regenerator system development. 130 figs., 12 tabs.

  1. A decision support system based on hybrid knowledge approach for nuclear power plant operation

    International Nuclear Information System (INIS)

    This paper describes a diagnostic expert system, HYPOSS (Hybrid Knowledge Based Plant Operation Supporting System), which has been developed to support operators' decision making during the transients of nuclear power plant. HYPOSS adopts the hybrid knowledge approach which combines shallow and deep knowledge to couple the merits of both approaches. In HYPOSS, four types of knowledge are used according to the steps of diagnosis procedure: structural, functional, behavioral and heuristic knowledge. Frames and rules are adopted to represent the various knowledge types. Rule-based deduction and abduction are used for shallow and deep knowledge based reasoning respectively. The event-based operational guidelines are provided to the operator according to the diagnosed results

  2. Human factors design review guidelines for advanced nuclear control room technologies

    International Nuclear Information System (INIS)

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

  3. Economic assessment of hybrid nuclear desalination demonstration project. Annex 5. India

    International Nuclear Information System (INIS)

    The technical and economic assessment of hybrid nuclear desalination project (Kalpakkam) has been discussed. The impact of pre-heat RO on the techno-economics of water production has been investigated with the help of design softwares and experimental studies. All the seawater membranes, considered for study, exhibited increase in water flux and reduction in solute rejection at higher temperatures. At higher temperature, operating at higher pressure is found to be more economical than operating at constant recovery. Studies were conducted on the usability of MSF reject streams as feed to RO and RO reject stream as feed to MSF. Based on the optimization studies on hybridization, it has been noted that, better quality drinking water at reasonable cost can be produced by combining RO and MSF in 1:2 ratio and by using the MSF coolant return water as feed to RO. Economic evaluation of integrated membrane system for seawater desalination has been carried out. Economic assessment on capacity scaling-up benefits of MSF and RO plants has been presented. Scale-up benefits in RO is marginal as it is modular in nature. Cost benefits due to scale-up are significant in the case of MSF. As energy cost constitutes a major fraction in MSF water cost, utilizing low grade heat or waste heat will reduce the production cost substantially. Experimental studies on nuclear desalination by using waste heat from the nuclear research reactor (CIRUS) for sea water desalination has been presented. (author)

  4. Fusion hybrids for generation of advanced (231Pa+232U+233U+234U)-fuel in closed (U-Pu-Th)-fuel cycle

    International Nuclear Information System (INIS)

    Technology of controlled thermonuclear fusion (CTF) is traditionally regarded as a practically inexhaustible energy source. However, development, mastering, broad deployment of fast breeder reactors and closure of nuclear fuel cycle (NFC) can also extend fuel base of nuclear power industry (NPI) up to practically unlimited scales. Under these conditions, it seems reasonable to introduce into a circle of the CTF-related studies the works directed towards solving some principal problems which can appear in a large-scale NPI in closed NFC. The first challenge is a large scale of operations in NFC back-end that should be reduced by achieving substantially higher fuel burn-up in power nuclear reactors. The use of 231Pa-232Th-232U-233U fuel in light-water reactor (LWR) opens a possibility of principle to reach very high (about 30% HM) or even ultra-high fuel burn-up. The second challenge is a potential unauthorized proliferation of fissionable materials. As is known, a certain remarkable quantity of 232U being introduced into uranium fraction of nuclear fuel can produce a serious barrier against switching the fuel over to non-energy purposes. Involvement of hybrid thermonuclear reactors (HTR) into NPI structure can substantially facilitate resolving these problems. If HTR will be involved into NPI structure, then main HTR mission consists not in energy generation but in production of nuclear fuel with a certain isotope composition. The present paper analyzes some neutron-physical features in production of advanced nuclear fuels in thorium HTR blankets. The obtained results demonstrated that such a nuclear fuel may be characterized by very stable neutron-multiplying properties during full LWR operation cycle and by enhanced proliferation resistance too. The paper evaluates potential benefits from involvement of HTR with thorium blanket into the international closed NFC. (author)

  5. 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.

  6. Hybridization during altitudinal range shifts: nuclear introgression leads to extensive cyto-nuclear discordance in the fire salamander.

    Science.gov (United States)

    Pereira, Ricardo J; Martínez-Solano, Iñigo; Buckley, David

    2016-04-01

    Ecological models predict that, in the face of climate change, taxa occupying steep altitudinal gradients will shift their distributions, leading to the contraction or extinction of the high-elevation (cold-adapted) taxa. However, hybridization between ecomorphologically divergent taxa commonly occurs in nature and may lead to alternative evolutionary outcomes, such as genetic merger or gene flow at specific genes. We evaluate this hypothesis by studying patterns of divergence and gene flow across three replicate contact zones between high- and low-elevation ecomorphs of the fire salamander (Salamandra salamandra) that have experienced altitudinal range shifts over the current postglacial period. Strong population structure with high genetic divergence in mitochondrial DNA suggests that vicariant evolution has occurred over several glacial-interglacial cycles and that it has led to cryptic differentiation within ecomorphs. In current parapatric boundaries, we do not find evidence for local extinction and replacement upon postglacial expansion. Instead, parapatric taxa recurrently show discordance between mitochondrial and nuclear markers, suggesting nuclear-mediated gene flow across contact zones. Isolation with migration models support this hypothesis by showing significant gene flow across all five parapatric boundaries. Together, our results suggest that, while some genomic regions, such as the mitochondria, may follow morphologic species traits and retreat to isolated mountain tops, other genomic regions, such as nuclear markers, may flow across parapatric boundaries, sometimes leading to a complete genetic merger. We show that despite high ecologic and morphologic divergence over prolonged periods of time, hybridization allows for evolutionary outcomes alternative to extinction and replacement of taxa in response to climate change. PMID:26850834

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

    International Nuclear Information System (INIS)

    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. These advanced critical robot technology and telepresence techniques developed in this project can be applied to nozzle-dam installation/removal robot system, can be used to realize unmanned remotelization of nozzle-dam installation/removal task in steam generator of nuclear power plant, which can be contributed for people involved in extremely hazardous

  8. Advances in zirconium technology for nuclear reactor application

    International Nuclear Information System (INIS)

    Zirconium alloys are extensively used as a material for cladding nuclear fuels and for making core structurals of water-cooled nuclear power reactors all over the world for generation of nearly 16 percent of the worlds electricity. Only four countries in the world, namely France, USA, Russia and India, have large zirconium industry and capability to manufacture reactor grade zirconium sponge, a number of zirconium alloys and a wide variety of structural components for water cooled nuclear reactor. The present paper summarises the status of zirconium technology and highlights the achievement of Nuclear Fuel Complex during the last ten years in developing a wide variety of zirconium alloys and components for water-cooled nuclear power programme

  9. Cosmic ray nuclear interactions and EAS-triggered families observed by the Chacaltaya hybrid experiment

    International Nuclear Information System (INIS)

    Longitudinal and lateral characteristics of the families detected by emulsion chambers in the hybrid experiment with AS-array at Mt. Chacaltaya are studied in detail. Although many groups discuss about an increase of the heavy component in primary cosmic-rays beyond the knee region, it is shown that the observed characteristics of the families accompanied by large shower size, Ne>106, can not be explained by an increase of heavy primaries alone. It is necessary to assume some changes of nuclear interaction in order to explain the observed characteristics of the air-showers accompanied by families

  10. Preliminary design and analysis on nuclear fuel cycle for fission-fusion hybrid spent fuel burner

    International Nuclear Information System (INIS)

    A wet-processing-based fuel cycle and a dry-processing were designed for a fission-fusion hybrid spent fuel burner (FDS-SFB). Mass flow of SFB was preliminarily analyzed. The feasibility analysis of initial loaded fuel inventory, recycle fuel fabrication and spent fuel reprocessing were preliminarily evaluated. The results of mass flow of FDS-SFB demonstrated that the initial loaded fuel inventory, recycle fuel fabrication and spent fuel reprocessing of nuclear fuel cycle of FDS-SFB is preliminarily feasible. (authors)

  11. Identification of bester hybrid and its parental species (♀ Huso huso Linnaeus, 1758 and ♂ Acipenser ruthenus Linnaeus, 1758 by nuclear markers

    Directory of Open Access Journals (Sweden)

    Andreea Dudu

    2015-05-01

    Full Text Available In Romania, sturgeon farming is gaining advance, different species being raised for commercial purposes and for restocking activities. A correct identification of individuals is imposed since severe ecological damages might occur if non-native species or hybrids are used for restocking. Such identification is required also for commercial reasons, the meat and caviar from different species having different prices. The aim of our study was to analyze two sturgeon species, Huso huso and Acipenser ruthenus and their interspecific hybrid - bester, using nuclear markers, in order to set up a molecular method for their accurate identification. The genetic pattern of the species was inferred from the analysis of nine microsatellite loci (LS19, LS34, LS39, LS54, AoxD234, AnacC11, LS68, Aox45 and Aox27 amplified by multiplex PCR reactions. The genotype data were analyzed with GENETIX v4.05 and STRUCTURE. The FCA analysis grouped the individuals in three distinct clusters corresponding to each of the pure species and to the interspecific hybrids. The admixture analysis performed in STRUCTURE also assigned three groups, confirming the results highlighted by FCA. We can conclude that the selected microsatellite markers allow the unambiguously identification of the bester hybrid and its genitor species from Romanian farms.

  12. NATO Advanced Study Institute on New Aspects of Nuclear Dynamics

    CERN Document Server

    Huberts, P

    1989-01-01

    The 1988 Summer School on New Aspects of Nuclear Dynamics took place in the style that by now has become a tradition: a series of lectures by well known scientists on modem topics of nuclear physics, where special emphasis is placed on the didactic aspects of the lectures. In the past few years, we have witnessed a rapid evolution of the field of nuclear physics towards novel directions of research. This development is accompanied by the construction of some of the largest experimental facilities ever built for nuclear research. The subjects covered by the Summer School focussed on two main issues currently under active investigation and which will be pursued with the new facilities: the transition from nucleonic to quark degrees of freedom in the decription of nuclear reactions, and the behavior of nuclear matter as one approaches extreme densities and temperatures. These topics in many respects go beyond traditional nuclear physics and the speakers therefore also included high energy physicists. From the re...

  13. Advanced charged particle beam ignited nuclear pulse propulsion

    Science.gov (United States)

    Winterberg, F.

    2009-06-01

    It is shown that the mass of the driver for nuclear microexplosion—Orion type—pulse propulsion can be substantially reduced with a special fusion-fast fission configuration, which permits to replace an inefficient laser beam driver with a much more efficient and less massive relativistic electron beam (or light ion beam) driver. The driver mass can be further reduced, and the propulsion efficiency increased, by surrounding the nuclear microexplosion assembly with a shell of conventional hydrogen-rich explosive, helping to ignite the nuclear reaction and dissipating the otherwise lost kinetic neutron energy in the shell which becomes part of the propellant.

  14. Coupling and control in coherently driven and asymmetrically synchronized hybrid electron-nuclear spin system

    Science.gov (United States)

    Berec, V.

    2016-02-01

    We study the coupling and control adaptation of a hybrid electron-nuclear spin system using the laser mediated proton beam in MeV energy regime. The asymmetric control mechanism is based on exact optimization of both: the measure of exchange interaction and anisotropy of the hyperfine interaction induced in the resonance with optimal channeled protons (CP) superfocused field, allowing manipulation over arbitrary localized spatial centers while addressing only the electron spin. Using highly precise and coherent proton channeling regime we have obtained efficient pulse shaping separator technique aimed for spatio-temporal engineering of quantum states, introducing a method for control of nuclear spins, which are coupled via anisotropic hyperfine interactions in isolated electron spin manifold, without radio wave (RW) pulses. The presented method can be efficiently implemented in synchronized spin networks with the purpose to facilitate preservation and efficient transfer of experimentally observed quantum particle states, contributing to the overall background noise reduction.

  15. Hybrid fusion reactor for production of nuclear fuel with minimum radioactive contamination of the fuel cycle

    Science.gov (United States)

    Velikhov, E. P.; Kovalchuk, M. V.; Azizov, E. A.; Ignatiev, V. V.; Subbotin, S. A.; Tsibulskiy, V. F.

    2015-12-01

    The paper presents the results of the system research on the coordinated development of nuclear and fusion power engineering in the current century. Considering the increasing problems of resource procurement, including limited natural uranium resources, it seems reasonable to use fusion reactors as high-power neutron sources for production of nuclear fuel in a blanket. It is shown that the share of fusion sources in this structural configuration of the energy system can be relatively small. A fundamentally important aspect of this solution to the problem of closure of the fuel cycle is that recycling of highly active spent fuel can be abandoned. Radioactivity released during the recycling of the spent fuel from the hybrid reactor blanket is at least two orders of magnitude lower than during the production of the same number of fissile isotopes after the recycling of the spent fuel from a fast reactor.

  16. Hybrid fusion reactor for production of nuclear fuel with minimum radioactive contamination of the fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Velikhov, E. P.; Kovalchuk, M. V.; Azizov, E. A., E-mail: Azizov-EA@nrcki.ru; Ignatiev, V. V.; Subbotin, S. A., E-mail: subbotinSA@dhtp.nrcki.ru; Tsibulskiy, V. F., E-mail: sibulskiy-VF@nrcki.ru [National Research Center Kurchatov Institute (Russian Federation)

    2015-12-15

    The paper presents the results of the system research on the coordinated development of nuclear and fusion power engineering in the current century. Considering the increasing problems of resource procurement, including limited natural uranium resources, it seems reasonable to use fusion reactors as high-power neutron sources for production of nuclear fuel in a blanket. It is shown that the share of fusion sources in this structural configuration of the energy system can be relatively small. A fundamentally important aspect of this solution to the problem of closure of the fuel cycle is that recycling of highly active spent fuel can be abandoned. Radioactivity released during the recycling of the spent fuel from the hybrid reactor blanket is at least two orders of magnitude lower than during the production of the same number of fissile isotopes after the recycling of the spent fuel from a fast reactor.

  17. Hybrid fusion reactor for production of nuclear fuel with minimum radioactive contamination of the fuel cycle

    International Nuclear Information System (INIS)

    The paper presents the results of the system research on the coordinated development of nuclear and fusion power engineering in the current century. Considering the increasing problems of resource procurement, including limited natural uranium resources, it seems reasonable to use fusion reactors as high-power neutron sources for production of nuclear fuel in a blanket. It is shown that the share of fusion sources in this structural configuration of the energy system can be relatively small. A fundamentally important aspect of this solution to the problem of closure of the fuel cycle is that recycling of highly active spent fuel can be abandoned. Radioactivity released during the recycling of the spent fuel from the hybrid reactor blanket is at least two orders of magnitude lower than during the production of the same number of fissile isotopes after the recycling of the spent fuel from a fast reactor

  18. Advanced Hybrid Spacesuit Concept Featuring Integrated Open Loop and Closed Loop Ventilation Systems

    Science.gov (United States)

    Daniel, Brian A.; Fitzpatrick, Garret R.; Gohmert, Dustin M.; Ybarra, Rick M.; Dub, Mark O.

    2013-01-01

    A document discusses the design and prototype of an advanced spacesuit concept that integrates the capability to function seamlessly with multiple ventilation system approaches. Traditionally, spacesuits are designed to operate both dependently and independently of a host vehicle environment control and life support system (ECLSS). Spacesuits that operate independent of vehicle-provided ECLSS services must do so with equipment selfcontained within or on the spacesuit. Suits that are dependent on vehicle-provided consumables must remain physically connected to and integrated with the vehicle to operate properly. This innovation is the design and prototype of a hybrid spacesuit approach that configures the spacesuit to seamlessly interface and integrate with either type of vehicular systems, while still maintaining the ability to function completely independent of the vehicle. An existing Advanced Crew Escape Suit (ACES) was utilized as the platform from which to develop the innovation. The ACES was retrofitted with selected components and one-off items to achieve the objective. The ventilation system concept was developed and prototyped/retrofitted to an existing ACES. Components were selected to provide suit connectors, hoses/umbilicals, internal breathing system ducting/ conduits, etc. The concept utilizes a lowpressure- drop, high-flow ventilation system that serves as a conduit from the vehicle supply into the suit, up through a neck seal, into the breathing helmet cavity, back down through the neck seal, out of the suit, and returned to the vehicle. The concept also utilizes a modified demand-based breathing system configured to function seamlessly with the low-pressure-drop closed-loop ventilation system.

  19. Hybrid laser/arc welding of advanced high strength steel in different butt joint configurations

    International Nuclear Information System (INIS)

    Highlights: • Feasibility of joining thick steel by HLAW process was studied. • Design of butt joint configurations satisfied ballistic test requirement. • Heat input and microstructure were changed by groove geometry. - Abstract: An experimental procedure was developed to join thick advanced high strength steel plates by using the hybrid laser/arc welding (HLAW) process, for different butt joint configurations. The geometry of the weld groove was optimized according to the requirements of ballistic test, where the length of the softened heat affected zone should be less than 15.9 mm from the weld centerline. The cross-section of the welds was examined by microhardness test. The microstructure of welds was investigated by scanning electron microscopy and an optical microscope for further analysis of the microstructure of fusion zone and heat affected zone. It was demonstrated that by changing the geometry of groove, and increasing the stand-off distance between the laser beam and the tip of wire in gas metal arc welding (GMAW) it is possible to reduce the width of the heat affected zone and softened area while the microhardness stays within the acceptable range. It was shown that double Y-groove shape can provide the optimum condition for the stability of arc and laser. The dimensional changes of the groove geometry provided substantial impact on the amount of heat input, causing the fluctuations in the hardness of the weld as a result of phase transformation and grain size. The on-line monitoring of HLAW of the advanced high strength steel indicated the arc and laser were stable during the welding process. It was shown that less plasma plume was formed in the case where the laser was leading the arc in the HLAW, causing higher stability of the molten pool in comparison to the case where the arc was leading

  20. Advances in Nuclear Power Technology : The U. S. Perspective

    International Nuclear Information System (INIS)

    Two months prior to signing the Atomic Energy Act of 1946, President Truman sent the following message to Congress : 'The hope of civilization lies in international arrangements (for) directing and encouraging the use of atomic energy and all future scientific information toward peaceful and humanitarian ends....' However, it took seven years of negotiations and compromises in the U. S. Congress, in international conferences, and in the United Nations before a meaningful framework for cooperation among nations could be established. Not until December 8, 1953, when President Eisenhower delivered his famous 'Atoms for Peace' speech before the United Nations General Assembly, was a plan for international nuclear cooperation delivered. With this initiative, the United States began an ambitious, and ultimately successful, program to promote the peaceful uses of nuclear technology. Today, over 400 nuclear power plants are in operation in 26 countries. Nuclear power can generate nearly 300,000 megawatts. This is a truly remarkable accomplishment

  1. Reference Operational Concepts for Advanced Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Hugo, Jacques Victor [Idaho National Lab. (INL), Idaho Falls, ID (United States); Farris, Ronald Keith [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-09-01

    This report represents the culmination of a four-year research project that was part of the Instrumentation and Control and Human Machine Interface subprogram of the DOE Advanced Reactor Technologies program.

  2. Advanced Passive Reactors : Leading The U. S. Nuclear Renaissance

    International Nuclear Information System (INIS)

    Twenty-one years have passed since Korea Electric Power Corporation and Westinghouse announced plans to build Kori 1. Today, Korea's nuclear program is one of the most successful in the world. The electricity generated from Kori 1 and eight other nuclear plants has helped to spark the remarkable growth and transformation of Korea into a modern industrial power. Westinghouse is proud to have been Korea's partner on six of those plants. It the past is the bast prophet of the future, then you and your countrymen should certainly be excited by your future. Korean industry is poised to continue its steady growth, and that means continued growth for your nuclear industry. Currently, the U. S. nuclear industry is experiencing a similar mood of excitement. In fact, it would be necessary to go almost all the way back to the beginning of the birth of the Korean nuclear industry, in 1969, to find a time when the future of nuclear power in the United States looked as bright as it does today. Part of our excitement stems from the welcome prospect of growth. In recent years, there has not been a market for new nuclear plants in the United States. Utilities either had excess capacity or were building plants they had ordered before 1974. For example, between 1980 and 1989, U. S. utilities completed 46 large nuclear units, but didn't order a single new one in that time. Since 1983, however, strong economic growth in the United States has caused the demand for electric power to grow about twice as fast as utilities had projected. Today, utilities will need to order new busload plants. When they do, utilities won't want technology developed 20 years ago. They'll be looking for plants that can meet the environmental, economic, and safety standards of the 21st century

  3. Proceedings of the symposium on advanced nuclear services

    International Nuclear Information System (INIS)

    This conference brought together representatives of Canadian nuclear power plant operators and members of private and public organizations offering services to nuclear power plant operators. The twenty papers discussed remotely operated tools and other equipment for reactor and cooling system inspection and maintenance; computer control systems; reactor simulators; improvements in the performance of pump seals, steam generators and valves; decontamination processes; and water chemistry control

  4. Hybrid particle swarm optimization algorithm and its application in nuclear engineering

    International Nuclear Information System (INIS)

    Highlights: • We propose a hybrid particle swarm optimization algorithm (HPSO). • Modified Nelder–Mead simplex search method is applied in HPSO. • The algorithm has a high search precision and rapidly calculation speed. • HPSO can be used in the nuclear engineering optimization design problems. - Abstract: A hybrid particle swarm optimization algorithm with a feasibility-based rule for solving constrained optimization problems has been developed in this research. Firstly, the global optimal solution zone can be obtained through particle swarm optimization process, and then the refined search of the global optimal solution will be achieved through the modified Nelder–Mead simplex algorithm. Simulations based on two well-studied benchmark problems demonstrate the proposed algorithm will be an efficient alternative to solving constrained optimization problems. The vertical electrical heating pressurizer is one of the key components in reactor coolant system. The mathematical model of pressurizer has been established in steady state. The optimization design of pressurizer weight has been carried out through HPSO algorithm. The results show the pressurizer weight can be reduced by 16.92%. The thermal efficiencies of conventional PWR nuclear power plants are about 31–35% so far, which are much lower than fossil fueled plants based in a steam cycle as PWR. The thermal equilibrium mathematic model for nuclear power plant secondary loop has been established. An optimization case study has been conducted to improve the efficiency of the nuclear power plant with the proposed algorithm. The results show the thermal efficiency is improved by 0.5%

  5. RECENT ADVANCES IN THE DEVELOPMENT OF THE HYBRID SULFUR PROCESS FOR HYDROGEN PRODUCTION

    Energy Technology Data Exchange (ETDEWEB)

    Hobbs, D.

    2010-07-22

    Thermochemical processes are being developed to provide global-scale quantities of hydrogen. A variant on sulfur-based thermochemical cycles is the Hybrid Sulfur (HyS) Process, which uses a sulfur dioxide depolarized electrolyzer (SDE) to produce the hydrogen. In the HyS Process, sulfur dioxide is oxidized in the presence of water at the electrolyzer anode to produce sulfuric acid and protons. The protons are transported through a cation-exchange membrane electrolyte to the cathode and are reduced to form hydrogen. In the second stage of the process, the sulfuric acid by-product from the electrolyzer is thermally decomposed at high temperature to produce sulfur dioxide and oxygen. The two gases are separated and the sulfur dioxide recycled to the electrolyzer for oxidation. The Savannah River National Laboratory (SRNL) has been exploring a fuel-cell design concept for the SDE using an anolyte feed comprised of concentrated sulfuric acid saturated with sulfur dioxide. The advantages of this design concept include high electrochemical efficiency and small footprint compared to a parallel-plate electrolyzer design. This paper will provide a summary of recent advances in the development of the SDE for the HyS process.

  6. A Soft-Switching Inverter for High-Temperature Advanced Hybrid Electric Vehicle Traction Motor Drives

    Energy Technology Data Exchange (ETDEWEB)

    Lai, Jason [Virginia Polytechnic Inst. and State Univ. (Virginia Tech), Blacksburg, VA (United States); Yu, Wensong [Virginia Polytechnic Inst. and State Univ. (Virginia Tech), Blacksburg, VA (United States); Sun, Pengwei [Virginia Polytechnic Inst. and State Univ. (Virginia Tech), Blacksburg, VA (United States); Leslie, Scott [Powerex, Inc., Harrison, OH (United States); Prusia, Duane [Powerex, Inc., Harrison, OH (United States); Arnet, Beat [Azure Dynamics, Oak Park, MI (United States); Smith, Chris [Azure Dynamics, Oak Park, MI (United States); Cogan, Art [Azure Dynamics, Oak Park, MI (United States)

    2012-03-31

    The state-of-the-art hybrid electric vehicles (HEVs) require the inverter cooling system to have a separate loop to avoid power semiconductor junction over temperatures because the engine coolant temperature of 105°C does not allow for much temperature rise in silicon devices. The proposed work is to develop an advanced soft-switching inverter that will eliminate the device switching loss and cut down the power loss so that the inverter can operate at high-temperature conditions while operating at high switching frequencies with small current ripple in low inductance based permanent magnet motors. The proposed tasks also include high-temperature packaging and thermal modeling and simulation to ensure the packaged module can operate at the desired temperature. The developed module will be integrated with the motor and vehicle controller for dynamometer and in-vehicle testing to prove its superiority. This report will describe the detailed technical design of the soft-switching inverters and their test results. The experiments were conducted both in module level for the module conduction and switching characteristics and in inverter level for its efficiency under inductive and dynamometer load conditions. The performance will be compared with the DOE original specification.

  7. HYDROTHERMALLY SELF-ADVANCING HYBRID COATINGS FOR MITIGATING CORROSION OF CARBON STEEL.

    Energy Technology Data Exchange (ETDEWEB)

    SUGAMA, T.

    2006-11-22

    Hydrothermally self-advancing hybrid coatings were prepared by blending two starting materials, water-borne styrene acrylic latex (SAL) as the matrix and calcium aluminate cement (CAC) as the hydraulic filler, and then their usefulness was evaluated as the room temperature curable anti-corrosion coatings for carbon steel in CO{sub 2}-laden geothermal environments at 250 C. The following two major factors supported the self-improving mechanisms of the coating during its exposure in an autoclave: First was the formation of a high temperature stable polymer structure of Ca-complexed carboxylate groups containing SAL (Ca-CCG-SAL) due to hydrothermal reactions between SAL and CAC; second was the growth with continuing exposure time of crystalline calcite and boehmite phases coexisting with Ca-CCG-SAL. These two factors promoted the conversion of the porous microstructure in the non-autoclaved coating into a densified one after 7 days exposure. The densified microstructure not only considerably reduced the conductivity of corrosive ionic electrolytes through the coatings' layers, but also contributed to the excellent adherence of the coating to underlying steel' s surface that, in turn, retarded the cathodic oxygen reduction reaction at the corrosion site of steel. Such characteristics including the minimum uptake of corrosive electrolytes by the coating and the retardation of the cathodic corrosion reaction played an important role in inhibiting the corrosion of carbon steel in geothermal environments.

  8. Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System

    OpenAIRE

    Kramer, Kevin James

    2010-01-01

    This study investigates the neutronics design aspects of a hybrid fusion-fission energy system called the Laser Fusion-Fission Hybrid (LFFH). A LFFH combines current Laser Inertial Confinement fusion technology with that of advanced fission reactor technology to produce a system that eliminates many of the negative aspects of pure fusion or pure fission systems. When examining the LFFH energy mission, a significant portion of the United States and world energy production could be supplied by ...

  9. Advances in nuclear chemistry and its applications in the Philippines

    International Nuclear Information System (INIS)

    Nuclear chemistry was born almost 120 years ago with the discovery of radioactivity by Antoine Henry Becquerel in 1896. Nuclear chemistry is a subfield of chemistry that deals with radioactivity, nuclear reactions and processes, and nuclear properties. The composition of the nucleus and the changes that occur within the nucleus define the properties of the radioisotope and the nuclear reactions and processes it is involved in. Almost six decades ago, nuclear chemistry established its roots in the Philippines under the Philippine Atomic Energy Commission, presently the Philippine Nuclear Research Institute. The main areas of nuclear chemistry, namely, namely radiochemistry, radiation chemistry, radiation biology, and isotopic chemistry have been studies, and have found applications in food and agriculture, medicine and health, in idustry, and in the protection of the environment. Early work in nuclear chemistry utilized the Philippine Research Reactor (PRR-1) for the production of radioisotopes which were used in either research or direct applications in food and agriculture, health and medicine, and industry. The PRR-1 provided neutrons for the non destructive multi element analysis of various samples using the neutron activation analysis technique. Radioactive materials as sources of ionizing radiation are being used extensively to study the chemical and biological effects of radiation on matter. Current studies involve the irradiation of certain plants and insects causing changes in their DNA which result in mutation for better crop varieties and sterility in insects for quarantine treatment and pest management. Radiation can modify the properties of polymers. Natural polymers such as carrageenan, chitosan and cellulose in abaca and water hyacinth fibers are subjected to gamma irradiation changing their properties and resulting in new products such as wound drressing, hemostatic agents, plant growth promoters, and metal-chelating agents. Radioisotopes are also

  10. A diagnostic expert system for the nuclear power plant b ased on the hybrid knowledge approach

    International Nuclear Information System (INIS)

    A diagnostic expert system, the hybrid knowledge based plant operation supporting system (HYPOSS), which has been developed to support operators' decisionmaking during the transients of the nuclear power plant, is described. HYPOSS adopts the hybrid knowledge approach, which combines both shallow and deep knowledge to take advantage of the merits of both approaches. In HYPOSS, four types of knowledge are used according to the steps of diagnosis procedure. They are structural, functional, behavioral, and heuristic knowledge. The structural and functional knowledge is represented by three fundamental primitives and five types of functions, respectively. The behavioral knowledge is represented using constraints. The inference procedure is based on the human problem-solving behavior modeled in HYPOSS. The event-based operational guidelines are provided to the operator according to the diagnosed results. If the exact anomalies cannot be identified while some of the critical safety functions are challenged, the function-based operational guidelines are provided to the operator. For the validation of HYPOSS, several tests have been performed based on the data produced by a plant simulator. The results of validation studies show good applicability of HYPOSS to the anomaly diagnosis of nuclear power plant

  11. Performance improvement of hybrid desalination system for coupling of nuclear reactors and desalination systems

    International Nuclear Information System (INIS)

    The objective of the research project is to study the behavior of Multi-Stage (MSF), Reverse Osmosis (RO) and Low Temperature Evaporation (LTE) desalination plants under different operating conditions and to utilize data for improving the performance of hybrid MSF-RO plant coupled to PHWR and LTE plant coupled to a nuclear research reactor. RO - (i) Study the performance of SWRO using sea water feed at different temperatures; (ii) Analysis of data collected on different membrane elements and projection; (iii) Collection of data in the 100 m3/d RO pilot plant. MSF - (i) Operation of 425 m3/d MSF plant and collection of data; (ii) To study the performance of MSF plant under different operating conditions of sea water temperature; (iii) Analysis of data LTE; (i) To study the performance of LTE plant at different temperatures of hot water required for sea water evaporation; (ii) Coupling of LTE plant set up at CIRUS. Utilization of the data for study of coupling aspects of the hybrid MSF-RO nuclear desalination demonstration plant, Kalpakkam

  12. On-line hybrid radiation dosimeter for the nuclear mobile robot (KAEROT/m2)

    International Nuclear Information System (INIS)

    The electronics of a mobile robot in nuclear facilities is required to satisfied the relibility to sustain survival in its radiation environment. To know how much radiation the robot has been encountered to replace sensitive electronic parts, a dosimeter to measure total accumulated does is necessary. Among many radiation dosimeters or detectors, semiconductor radiation sensors have advantages in terms of power requirements and their sizes over conventional detectors. This paper describes the use of the radiation-induced threshold voltage change of a commercial power pMOSFET as an accumulated radiation dose monitoring mean and that of the photo-current of a commercial PIN Diode as a dose-rate measurement mean. Commercial p-type power MOSFETs and PIN Diodes were tested in a Co-60 gamma irradiation facility to see their capabilities as radiation sensors. We found an inexpensive commercial power pMOSFET that shows good linearity in their threshold voltage shift with radiation dose and a PIN diode that shows good linearity in its photo-current change with dose-rate. According to these findings, a radiation hardened hybrid electronic radiation dosimeter for nuclear robots has been developed for the first time. This small hybrid dosimeter has also an advantage in the point of view of reliability improvement by using a diversity concept

  13. The Economic Potential of Two Nuclear-Renewable Hybrid Energy Systems

    Energy Technology Data Exchange (ETDEWEB)

    Ruth, Mark [National Renewable Energy Lab. (NREL), Golden, CO (United States); Cutler, Dylan [National Renewable Energy Lab. (NREL), Golden, CO (United States); Flores-Espino, Francisco [National Renewable Energy Lab. (NREL), Golden, CO (United States); Stark, Greg [National Renewable Energy Lab. (NREL), Golden, CO (United States); Jenkin, Thomas [National Renewable Energy Lab. (NREL), Golden, CO (United States); Simpkins, Travis [National Renewable Energy Lab. (NREL), Golden, CO (United States); Macknick, Jordan [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2016-08-01

    Tightly coupled nuclear-renewable hybrid energy systems (N-R HESs) are an option that can generate zero-carbon, dispatchable electricity and provide zero-carbon energy for industrial processes at a lower cost than alternatives. N-R HESs are defined as systems that are managed by a single entity and link a nuclear reactor that generates heat, a thermal power cycle for heat to electricity conversion, at least one renewable energy source, and an industrial process that uses thermal and/or electrical energy. This report provides results of an analysis of two N-R HES scenarios. The first is a Texas-synthetic gasoline scenario that includes four subsystems: a nuclear reactor, thermal power cycle, wind power plant, and synthetic gasoline production technology. The second is an Arizona-desalination scenario with its four subsystems a nuclear reactor, thermal power cycle, solar photovoltaics, and a desalination plant. The analysis focuses on the economics of the N-R HESs and how they compare to other options, including configurations without all the subsystems in each N-R HES and alternatives where the energy is provided by natural gas.

  14. Analysis of prospects for advanced nuclear reactors in western countries

    International Nuclear Information System (INIS)

    Nuclear energy deployment faces stagnation in western european and north american countries as a result of barriers that have appeared over the years. Such barriers were identified in the domains of economics, public acceptance, energy policy, technology, licensing and regulations as well as environment and waste disposal. It is to the nuclear community and particularly the industry to take the initiative and the leadership role for the most significant approaches to overcome these barriers. These approaches include concentration of efforts, lowering of costs and financial risks and extensive use of the experience accumulated so far; clear setting of priorities and long-term global consideration of the energy issue; encouraging an appropriate, stable regulatory environment and harmonization of general safety objectives and principles, and adequate, globally consistent and clear information to the public. Also within the prime responsibility of the nuclear community belong the safe operation of existing plants; making available all necessary information to the public, the media and the political leaders, supporting the development and execution of national energy policies; supporting authorities in improving regulatory processes; taking all measures to improve economics of nuclear power; pursuing plans for the safe disposal of radioactive wastes. Governments should place energy issues in the appropriate priority level and encourage the establishment of an equally favourable environment for nuclear energy, including a greater consensus among controversial opinion representatives. Finally, authorities should established reasonable, transparent and predictable regulatory enviroments. This paper describes the barriers in a systematic way and proposes appropriate measures to overcame them

  15. Current Status of Advanced Nuclear Fuel Cycle technologies

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  17. NATO Advanced Research Workshop on Preparedness for Nuclear and Radiological Threats

    CERN Document Server

    Diamond, David

    2015-01-01

    The nuclear crisis in Fukushima and growing threats of nuclear terrorism must serve as a wake-up call, prompting greater action to prepare ourselves for nuclear and radiological disasters. Our strategy to prepare for these threats is multi-layered and the events of these past years have proved the necessity to re-evaluate the national and international preparedness goals on a scale never before considered. The programme of NATO Advanced Research Workshop on “Preparedness for Nuclear and Radiological Threats” has been focused on science and technology challenges associated with our need to improve the national and international capacity and capability to prevent, protect against, mitigate the effects of, respond to, and recover from the nuclear and radiological disasters, including nuclear and radiological accident, terrorist attack by Improvised Nuclear Device (IND) or by “Dirty Bomb”-Radiological Dispersal Device (RDD), that pose the greatest risk to the national and international security and safety...

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

    CERN Document Server

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

    2010-01-01

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

  19. Advanced methods for nuclear reactor gas laser coupling

    International Nuclear Information System (INIS)

    Research is described that led to the discovery of three nuclear-pumped lasers (NPLs) using mixtures of Ne--N2, He--Hg, and He or Ne with CO or CO2. The Ne--N2 NPL was the first laser obtained with modest neutron fluxes from a TRIGA reactor (vs fast burst reactors used elsewhere in such work), the He--Hg NPL was the first visible nuclear-pumped laser, while the Ne--CO and He--CO2 lasers are the first to provide energy storage on a millisecond time scale. Important potential applications of NPLs include coupling and power transmission from remote power stations such as nuclear plants in satellites and neutron-feedback operation of inertial confinement fusion plants

  20. Recent Advances in Nuclear Powered Electric Propulsion for Space Exploration

    Science.gov (United States)

    Cassady, R. Joseph; Frisbee, Robert H.; Gilland, James H.; Houts, Michael G.; LaPointe, Michael R.; Maresse-Reading, Colleen M.; Oleson, Steven R.; Polk, James E.; Russell, Derrek; Sengupta, Anita

    2007-01-01

    Nuclear and radioisotope powered electric thrusters are being developed as primary in-space propulsion systems for potential future robotic and piloted space missions. Possible applications for high power nuclear electric propulsion include orbit raising and maneuvering of large space platforms, lunar and Mars cargo transport, asteroid rendezvous and sample return, and robotic and piloted planetary missions, while lower power radioisotope electric propulsion could significantly enhance or enable some future robotic deep space science missions. This paper provides an overview of recent U.S. high power electric thruster research programs, describing the operating principles, challenges, and status of each technology. Mission analysis is presented that compares the benefits and performance of each thruster type for high priority NASA missions. The status of space nuclear power systems for high power electric propulsion is presented. The paper concludes with a discussion of power and thruster development strategies for future radioisotope electric propulsion systems,

  1. Recent advances in nuclear powered electric propulsion for space exploration

    Energy Technology Data Exchange (ETDEWEB)

    Cassady, R. Joseph [Aerojet Corp., Redmond, CA (United States); Frisbee, Robert H. [Jet Propulsion Laboratory, Pasadena, CA (United States); Gilland, James H. [Ohio Aerospace Institute, Cleveland, OH (United States); Houts, Michael G. [NASA Marshall Space Flight Center, Huntsville, AL 35812 (United States); LaPointe, Michael R. [NASA Marshall Space Flight Center, Huntsville, AL 35812 (United States)], E-mail: michael.r.lapointe@nasa.gov; Maresse-Reading, Colleen M. [Jet Propulsion Laboratory, Pasadena, CA (United States); Oleson, Steven R. [NASA Glenn Research Center, Cleveland, OH (United States); Polk, James E. [Jet Propulsion Laboratory, Pasadena, CA (United States); Russell, Derrek [Northrop Grumman Space Technology, Redondo Beach, CA (United States); Sengupta, Anita [Jet Propulsion Laboratory, Pasadena, CA (United States)

    2008-03-15

    Nuclear and radioisotope powered electric thrusters are being developed as primary in space propulsion systems for potential future robotic and piloted space missions. Possible applications for high-power nuclear electric propulsion include orbit raising and maneuvering of large space platforms, lunar and Mars cargo transport, asteroid rendezvous and sample return, and robotic and piloted planetary missions, while lower power radioisotope electric propulsion could significantly enhance or enable some future robotic deep space science missions. This paper provides an overview of recent US high-power electric thruster research programs, describing the operating principles, challenges, and status of each technology. Mission analysis is presented that compares the benefits and performance of each thruster type for high priority NASA missions. The status of space nuclear power systems for high-power electric propulsion is presented. The paper concludes with a discussion of power and thruster development strategies for future radioisotope electric propulsion systems.

  2. Advances in the understanding of inter-subspecific hybrid sterility and wide-compatibility in rice

    Institute of Scientific and Technical Information of China (English)

    OUYANG YiDan; CHEN JiongJiong; DING JiHua; ZHANG QiFa

    2009-01-01

    Hybrid sterility is a major form of postzygotic reproductive isolation and frequently occurs in hybrids between divergent populations, such as the indica and japonica subspecies of Asian cultivated rice (Oryza sativa L.). It has been a major barrier for utilization of the strong heterosis expressed in hybrids between indica and japonica. A large number of loci for rice inter-subspecific hybrid sterility have been identified by genetic analysis. Cytological studies revealed that male and female gamete abortions and reduced affinity between the uniting gametes all occurred in indica-japonica hybrids, suggesting the complexity of the causes for inter-subspecific hybrid sterility. Two genes conditioning embryo-sac and pollen sterility respectively in indica-japonica hybrids have been cloned recently, providing opportunities for molecular characterization of the indica-japonica hybrid sterility and wide-compatibility. Future studies should aim at cloning more genes for indica-japonica hybrid sterility, characterizing the underlying molecular mechanism, and utilization of the findings for the development of inter-subspecific hybrids to increase rice productivity.

  3. Development of nuclear fuel. Development of CANDU advanced fuel bundle

    International Nuclear Information System (INIS)

    In order to develop CANDU advanced fuel, the agreement of the joint research between KAERI and AECL was made on February 19, 1991. AECL conceptual design of CANFLEX bundle for Bruce reactors was analyzed and then the reference design and design drawing of the advanced fuel bundle with natural uranium fuel for CANDU-6 reactor were completed. The CANFLEX fuel cladding was preliminarily investigated. The fabricability of the advanced fuel bundle was investigated. The design and purchase of the machinery tools for the bundle fabrication for hydraulic scoping tests were performed. As a result of CANFLEX tube examination, the tubes were found to be meet the criteria proposed in the technical specification. The dummy bundles for hydraulic scoping tests have been fabricated by using the process and tools, where the process parameters and tools have been newly established. (Author)

  4. Fusion--fision hybrid breeders: economic and performance issues, role of advanced converters, interdependence between fission and fusion programs

    International Nuclear Information System (INIS)

    This paper considers nuclear breeding systems (i.e., production of fissile fuel from fertile materials). The range of breeding technologies considered is deliberately wide. We include systems which breed by using internal neutron sources--a reactor-breeder, exemplified by the liquid metal fast breeder reactor (LMFBR)--and systems which breed by using external neutron sources--exemplified in this paper primarily by hybrid fusion-fission breeders

  5. High accuracy modeling for advanced nuclear reactor core designs using Monte Carlo based coupled calculations

    Science.gov (United States)

    Espel, Federico Puente

    The main objective of this PhD research is to develop a high accuracy modeling tool using a Monte Carlo based coupled system. The presented research comprises the development of models to include the thermal-hydraulic feedback to the Monte Carlo method and speed-up mechanisms to accelerate the Monte Carlo criticality calculation. Presently, deterministic codes based on the diffusion approximation of the Boltzmann transport equation, coupled with channel-based (or sub-channel based) thermal-hydraulic codes, carry out the three-dimensional (3-D) reactor core calculations of the Light Water Reactors (LWRs). These deterministic codes utilize nuclear homogenized data (normally over large spatial zones, consisting of fuel assembly or parts of fuel assembly, and in the best case, over small spatial zones, consisting of pin cell), which is functionalized in terms of thermal-hydraulic feedback parameters (in the form of off-line pre-generated cross-section libraries). High accuracy modeling is required for advanced nuclear reactor core designs that present increased geometry complexity and material heterogeneity. Such high-fidelity methods take advantage of the recent progress in computation technology and coupled neutron transport solutions with thermal-hydraulic feedback models on pin or even on sub-pin level (in terms of spatial scale). The continuous energy Monte Carlo method is well suited for solving such core environments with the detailed representation of the complicated 3-D problem. The major advantages of the Monte Carlo method over the deterministic methods are the continuous energy treatment and the exact 3-D geometry modeling. However, the Monte Carlo method involves vast computational time. The interest in Monte Carlo methods has increased thanks to the improvements of the capabilities of high performance computers. Coupled Monte-Carlo calculations can serve as reference solutions for verifying high-fidelity coupled deterministic neutron transport methods

  6. Advances in reprocessing technology to minimise nuclear fuel waste

    International Nuclear Information System (INIS)

    The responsible and effective management of nuclear wastes generated throughout the nuclear fuel cycle is the key element underpinning the current and future credibility of the industry. This paper presents an overview of the development of existing Purex reprocessing technology in the context of minimising waste streams arising from spent fuel reprocessing. These developments are presented in relation to BNFL's Thorp facility, designed for the reprocessing of oxide fuels. The paper proceeds to discuss potential opportunities for further waste reductions offered by radical reprocessing technologies, such as molten salts conditioning. (author)

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

    International Nuclear Information System (INIS)

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

  8. Laser Intertial Fusion Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System

    Energy Technology Data Exchange (ETDEWEB)

    Kramer, Kevin James [Univ. of California, Berkeley, CA (United States)

    2010-04-08

    This study investigates the neutronics design aspects of a hybrid fusion-fission energy system called the Laser Fusion-Fission Hybrid (LFFH). A LFFH combines current Laser Inertial Confinement fusion technology with that of advanced fission reactor technology to produce a system that eliminates many of the negative aspects of pure fusion or pure fission systems. When examining the LFFH energy mission, a significant portion of the United States and world energy production could be supplied by LFFH plants. The LFFH engine described utilizes a central fusion chamber surrounded by multiple layers of multiplying and moderating media. These layers, or blankets, include coolant plenums, a beryllium (Be) multiplier layer, a fertile fission blanket and a graphite-pebble reflector. Each layer is separated by perforated oxide dispersion strengthened (ODS) ferritic steel walls. The central fusion chamber is surrounded by an ODS ferritic steel first wall. The first wall is coated with 250-500 μm of tungsten to mitigate x-ray damage. The first wall is cooled by Li17Pb83 eutectic, chosen for its neutron multiplication and good heat transfer properties. The Li17Pb83 flows in a jacket around the first wall to an extraction plenum. The main coolant injection plenum is immediately behind the Li17Pb83, separated from the Li17Pb83 by a solid ODS wall. This main system coolant is the molten salt flibe (2LiF-BeF2), chosen for beneficial neutronics and heat transfer properties. The use of flibe enables both fusion fuel production (tritium) and neutron moderation and multiplication for the fission blanket. A Be pebble (1 cm diameter) multiplier layer surrounds the coolant injection plenum and the coolant flows radially through perforated walls across the bed. Outside the Be layer, a fission fuel layer comprised of depleted uranium contained in Tristructural-isotropic (TRISO) fuel particles

  9. Laser Intertial Fusion Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System

    Energy Technology Data Exchange (ETDEWEB)

    Kramer, K

    2010-04-08

    This study investigates the neutronics design aspects of a hybrid fusion-fission energy system called the Laser Fusion-Fission Hybrid (LFFH). A LFFH combines current Laser Inertial Confinement fusion technology with that of advanced fission reactor technology to produce a system that eliminates many of the negative aspects of pure fusion or pure fission systems. When examining the LFFH energy mission, a significant portion of the United States and world energy production could be supplied by LFFH plants. The LFFH engine described utilizes a central fusion chamber surrounded by multiple layers of multiplying and moderating media. These layers, or blankets, include coolant plenums, a beryllium (Be) multiplier layer, a fertile fission blanket and a graphite-pebble reflector. Each layer is separated by perforated oxide dispersion strengthened (ODS) ferritic steel walls. The central fusion chamber is surrounded by an ODS ferritic steel first wall. The first wall is coated with 250-500 {micro}m of tungsten to mitigate x-ray damage. The first wall is cooled by Li{sub 17}Pb{sub 83} eutectic, chosen for its neutron multiplication and good heat transfer properties. The {sub 17}Pb{sub 83} flows in a jacket around the first wall to an extraction plenum. The main coolant injection plenum is immediately behind the Li{sub 17}Pb{sub 83}, separated from the Li{sub 17}Pb{sub 83} by a solid ODS wall. This main system coolant is the molten salt flibe (2LiF-BeF{sub 2}), chosen for beneficial neutronics and heat transfer properties. The use of flibe enables both fusion fuel production (tritium) and neutron moderation and multiplication for the fission blanket. A Be pebble (1 cm diameter) multiplier layer surrounds the coolant injection plenum and the coolant flows radially through perforated walls across the bed. Outside the Be layer, a fission fuel layer comprised of depleted uranium contained in Tristructural-isotropic (TRISO) fuel particles having a packing fraction of 20% in 2 cm

  10. Performance of advanced high-temperature fuels for nuclear propulsion

    Energy Technology Data Exchange (ETDEWEB)

    Stark, W.A.; Butt, D.P.; Storms, E.K.; Wallace, T.C. [Los Alamos National Lab., NM (United States)

    1994-12-31

    Nuclear propulsion using hydrogen has been demonstrated to operate at nearly twice the performance level of today`s chemical rockets. However, higher temperatures lead to a variety of degradations that compromise safety and longevity. Foremost among these is the melting of the propulsion reactor fuel. The melting behaviour of the U-Zr-C and U-Nb-C systems have been evaluated.

  11. Advances in NASA's Nuclear Thermal Propulsion Technology project

    Science.gov (United States)

    Peecook, Keith M.; Stone, James R.

    1993-01-01

    The status of the Nuclear Thermal Propulsion (NTP) project for space exploration and the future plans for NTP technology are discussed. Current activities in the framework of the NTP project deal with nonnuclear material tests; instrumentation, controls, and health management; turbopumps; nozzles and nozzle extension; and an exhaust plume.

  12. Fabrication of Hybrid Nanostructures via Nanoscale Laser-Induced Reshaping for Advanced Light Manipulation.

    Science.gov (United States)

    Zuev, Dmitry A; Makarov, Sergey V; Mukhin, Ivan S; Milichko, Valentin A; Starikov, Sergey V; Morozov, Ivan A; Shishkin, Ivan I; Krasnok, Alexander E; Belov, Pavel A

    2016-04-01

    Ordered hybrid nanostructures for nanophotonics applications are fabricated by a novel approach via femtosecond laser melting of asymmetric metal-dielectric (Au/Si) nanoparticles created by lithographical methods. The approach allows selective reshaping of the metal components of the hybrid nanoparticles without affecting the dielectric ones and is applied for tuning of the scattering properties of the hybrid nanostructures in the visible range. PMID:26901635

  13. Needs of nuclear data for advanced light water reactor

    International Nuclear Information System (INIS)

    Hitachi has been developing medium sized ABWRs as a power source that features flexibility to meet various market needs, such as minimizing capital risks, providing a timely return on capital investments, etc. Basic design concepts of the medium sized ABWRs are 1) using the current ABWR design which has accumulated favorable construction and operation histories as a starting point; 2) utilizing standard BWR fuels which have been fabricated by proven technology; 3) achieving a rationalized design by suitably utilizing key components developed for large sized reactors. Development of the medium sized ABWRs has proceeded in a systematic, stepwise manner. The first step was to design an output scale for the 600MWe class reactor (ABWR-600), and the next step was to develop an uprating concept to extend this output scale to the 900MWe class reactor (ABWR-900) based on the rationalized technology of the ABWR-600 for further cost savings. In addition, Hitachi and MHI developed an ultra small reactor, 'Package-Reactor'. About the nuclear data, for the purpose of verification of the nuclear analysis method of BWR for mixed oxide (MOX) cores, UO2 and MOX fuel critical experiments EPICURE and MISTRAL were analyzed using nuclear design codes HINES and CERES with ENDF/B nuclear data file. The critical keffs of the absorber worth experiments, the water hole worth experiments and the 2D void worth experiments agreed with those of the reference experiments within about 0.1%Δk. The root mean square differences of radial power distributions between calculation and measurement were almost less than 2.0%. The calculated reactivity worth values of the absorbers, the water hole and the 2D void agreed with the measured values within nearly experimental uncertainties. These results indicate that the nuclear analysis method of BWR in the present paper give the same accuracy for the UO2 cores and the MOX cores. (author)

  14. Applying Best Practices of the US-Russian Nuclear Security Cooperation to Advancing a Global Nuclear Security Agenda

    International Nuclear Information System (INIS)

    US-Russian cooperation in nuclear security provides valuable insight and recommendations on how to establish bilateral and multilateral cooperative programs to improve nuclear security in other regions. It also creates a potential for a joint US-Russian engagement in addressing global nuclear security needs, particularly in regions where resources and capacities are limited. These recommendations can promote success and sustainability for potential multilateral cooperation on nuclear security, including within the framework of the G-8 Global Partnership, UNSCR 1540 implementation, IAEA-led efforts and various bilateral and regional arrangements. With this goal in mind, the team of researchers from CENESS, CNS, and VCDNP examined the most successful US-Russian cooperative programs and nuclear security needs in Southeast Asia and former Soviet republics--two regions in need of further strengthening of nuclear security infrastructure and arrangements. They identified a number of areas in which the experience and expertise gained during US-Russian cooperative threat reduction efforts could provide the most valuable input to advancing nuclear security goals. The following five areas were identified: 1) education and training of nuclear security specialists, 2) legal and institutional framework developments, 3) border controls, 4) strategic trade controls, and 5) radiological source control and management. (author)

  15. Neutronics analyses for fast spectrum nuclear systems and scenario studies for advanced nuclear fuel cycles

    OpenAIRE

    Grasso, Giacomo

    2010-01-01

    The present PhD thesis summarizes the three-years study about the neutronic investigation of a new concept nuclear reactor aiming at the optimization and the sustainable management of nuclear fuel in a possible European scenario. A new generation nuclear reactor for the nuclear reinassance is indeed desired by the actual industrialized world, both for the solution of the energetic question arising from the continuously growing energy demand together with the corresponding reduction of oil ava...

  16. Pore formation and its mitigation during hybrid laser/arc welding of advanced high strength steel

    International Nuclear Information System (INIS)

    Highlights: • Possible mechanisms of pores formation in HLAW of AHSS were studied. • Mitigation approaches for removing pores in AHSS welds were introduced. • Dx in HLAW and laser welding assisted with hot wire were alleviating pores. - Abstract: The possible mechanisms of the pores formation and their mitigation during the hybrid laser/arc welding (HLAW) of Advanced High Strength Steel (AHSS) were investigated. Influence of three variables (stand-off distance between the laser and the arc of gas metal arc welding (GMAW), heat input and side shielding gas) in the HLAW for reducing the presence of pores in the weld area was studied. The optimum condition of the welds prepared by the HLAW was compared with the welds made by the laser welding assisted with hot wire. The vision monitoring of the welding processes was performed by a charged coupled device (CCD) camera and mechanical properties of the welds were evaluated by a high energy impact test and microhardness measurement. The joints were characterized by the scanning electron microscopy (SEM) analysis and energy dispersive X-ray spectroscopy (EDS) analysis. The results showed that the optimum stand-off distance between the laser and the tip of wire in the HLAW and laser welding assisted with a hot wire were the most effective approaches for avoiding the pore formation. The fracture surface of the welds was mostly dominated by a brittle fracture with the presence of two types of pores, indicating that there were two mechanisms for the generation of pores in the weld area

  17. Advanced Hybrid On-Board Data Processor - SpaceCube 2.0 Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Develop advanced on-board processing to meet the requirements of the Decadal Survey missions: advanced instruments (hyper-spectral, SAR, etc) require advanced...

  18. Siemens' steam turbine generator packages for advanced nuclear power plants

    International Nuclear Information System (INIS)

    Despite the current economic crisis and the increasing share of renewable energy, the long term perspective predicts an increasing global demand for nuclear power generation applications. [1] In response to the growing demand for new nuclear power plants (NPPs), Siemens is implementing and further developing a modular platform of half speed steam turbines and generators covering the most relevant power range from 1000 - 1900 MWe. The paper presents details of the Siemens' Steam Turbine Generator Packages (turboset - Fig. 1) consisting of: Modular Steam Turbine Platform: SST-9000 series 4 pole turbo generator fleet SGEN5-4000W The design of the turbosets for NPPs is based on excellent operational experience with Siemens KONVOI saturated steam turbosets together with service and retrofit experience as well as on experience gained during the project execution of the world largest turboset in Olkiluoto 3. (orig.)

  19. Proliferation resistance of advanced sustainable nuclear fuel cycles

    International Nuclear Information System (INIS)

    Intrinsic and extrinsic proliferation barriers of a pyro-process-based nuclear fuel cycle are discussed. While technical characteristics of the process raise new challenges for safeguards, others naturally facilitate the implementation of more integrated schemes for unattended continuous monitoring. In particular, the concept of operations accountability and model-assisted methods are revisited. While traditional safeguards constructs, such as material control and accountability, place greater emphasis on input/output characterization of nuclear processes, a model- based discrete event accountability approach could explicitly verify not only facility use but also internal operational dynamics. Under the proposed remote integral safeguards approach, transparency can be achieved efficiently, without divulging competitive or national security sensitive information. (author)

  20. Human Factors Engineering Review Model for advanced nuclear power reactors

    Energy Technology Data Exchange (ETDEWEB)

    O`Hara, J.; Higgins, J. [Brookhaven National Lab., Upton, NY (United States); Goodman, C.; Galletti, G.: Eckenrode, R. [Nuclear Regulatory Commission, Rockville, MD (United States)

    1993-05-01

    One of the major issues to emerge from the initial design reviews under the certification process was that detailed human-systems interface (HSI) design information was not available for staff review. To address the lack of design detail issue. The Nuclear Regulatory Commission (NRC) is performing the design certification reviews based on a design process plan which describes the human factors engineering (HFE) program elements that are necessary and sufficient to develop an acceptable detailed design specification. Since the review of a design process is unprecedented in the nuclear industry. The criteria for review are not addressed by current regulations or guidance documents and. therefore, had to be developed. Thus, an HFE Program Review Model was developed. This paper will describe the model`s rationale, scope, objectives, development, general characteristics. and application.

  1. Development of advanced RFID application system for nuclear power plant

    International Nuclear Information System (INIS)

    In late years there comes to be close request for traceability of the information such as production control, construction and maintenance record and work history of nuclear power plants. On the other hand, the Radio-frequency identification (RFID) technology that can specify a product and personnel by an electric wave has raised the functionality and versatility as the base technology that can support ubiquitous information society around the mass production industry. In such a background, this article described the developed system, which applied the RFID to nuclear power plants in the areas of production control of the piping manufacture, the construction management and condition monitoring for maintenance works in order to improve their quality and reliability. (T. Tanaka)

  2. 4+D digital engineering for advanced nuclear energy systems

    International Nuclear Information System (INIS)

    Nuclear power plants (NPPs) require massive quantity of data during the design, construction, operation, maintenance and decommissioning stages because of their special features like size, cost, radioactivity, and so forth. The system engineering thus calls for a fully automated way of managing the information flow spanning their life cycle. In line with practice in disciplines of naval architecture, aerospace engineering, and automotive manufacturing, the paper proposes total digital systems engineering based on three-dimensional (3D) computer-aided design (CAD) models. The signature in the proposal lies with the four-plus-dimensional (4+D) TechnologyTM, a critical know-how for digital management. The so-called OPIUM (Optimized Plant Integrated Ubiquitous Management) features a 4+D TechnologyTM for nuclear energy systems engineering. The technology proposed in the 3D space and time plus cost coordinates, i.e. 4+D, is the backbone of digital engineering in the nuclear systems design and management. Based on an integrated 3D configuration management system, OPIUM consists of solutions NOTUS (Nuclear Optimization Technique Ubiquitous System), VENUS (Virtual Engineering Nuclear Ubiquitous System), INUUS (Informatics Nuclear Utilities Ubiquitous System), JANUS (Junctional Analysis Numerical Ubiquitous System) and EURUS (Electronic Unit Research Ubiquitous System). These solutions will help initial simulation capability for NPPs to supply the crucial information. NOTUS contributes to reducing the construction cost of the NPPs by optimizing the component manufacturing procedure and the plant construction process. Planning and scheduling construction projects can thus benefit greatly by integrating traditional management techniques with digital process simulation visualization. The 3D visualization of construction processes and the resulting products intrinsically afford most of the advantages realized by incorporating a purely schedule level detail based the 4+D system

  3. AP1000, a nuclear central of advanced design

    International Nuclear Information System (INIS)

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

  4. Human Factors Engineering Review Model for advanced nuclear power reactors

    International Nuclear Information System (INIS)

    One of the major issues to emerge from the initial design reviews under the certification process was that detailed human-systems interface (HSI) design information was not available for staff review. To address the lack of design detail issue. The Nuclear Regulatory Commission (NRC) is performing the design certification reviews based on a design process plan which describes the human factors engineering (HFE) program elements that are necessary and sufficient to develop an acceptable detailed design specification. Since the review of a design process is unprecedented in the nuclear industry. The criteria for review are not addressed by current regulations or guidance documents and. therefore, had to be developed. Thus, an HFE Program Review Model was developed. This paper will describe the model's rationale, scope, objectives, development, general characteristics. and application

  5. 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.

  6. South Ukraine Nuclear Power Plant. Advanced Computer Information System Project

    International Nuclear Information System (INIS)

    The South Ukraine upgrade is the first of many that will take place in the former eastern bloc countries over the next several years. Westron is currently developing a similar system for the Zaporozhe nuclear power plant. In addition, there are eleven other WWER type units in operation in the Ukraine, as well as twenty seven others in operation throughout Eastern and Central Europe and Russia - all potential upgrade projects. (author)

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

    International Nuclear Information System (INIS)

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

  8. Advanced nuclear fuel cycles - Main challenges and strategic choices

    International Nuclear Information System (INIS)

    A graphical conceptual model of the uranium fuel cycles has been developed to capture the present, anticipated, and potential (future) nuclear fuel cycle elements. The once-through cycle and plutonium recycle in fast reactors represent two basic approaches that bound classical options for nuclear fuel cycles. Chief among these other options are mono-recycling of plutonium in thermal reactors and recycling of minor actinides in fast reactors. Mono-recycling of plutonium in thermal reactors offers modest savings in natural uranium, provides an alternative approach for present-day interim management of used fuel, and offers a potential bridging technology to development and deployment of future fuel cycles. In addition to breeder reactors' obvious fuel sustainability advantages, recycling of minor actinides in fast reactors offers an attractive concept for long-term management of the wastes, but its ultimate value is uncertain in view of the added complexity in doing so,. Ultimately, there are no simple choices for nuclear fuel cycle options, as the selection of a fuel cycle option must reflect strategic criteria and priorities that vary with national policy and market perspectives. For example, fuel cycle decision-making driven primarily by national strategic interests will likely favor energy security or proliferation resistance issues, whereas decisions driven primarily by commercial or market influences will focus on economic competitiveness

  9. 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.

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

    International Nuclear Information System (INIS)

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

  11. Using the DSNP Modular Modeling System for the Safety Assessment of Advanced Nuclear Power Plants

    International Nuclear Information System (INIS)

    Advanced nuclear reactor concepts require even in their inception or preliminary conceptual design a safety assessment and a coupled neutronic-thermal hydraulic analysis. Often, such analyses cannot be performed with standard system analysis and simulation codes, because in most cases advanced reactor concepts, particularly in what is considered to be Gen-IV rectors, include unusual design features, which cannot be modeled with available simulation packages. The unusual features can be specially designed heat exchangers integrated in the core vessel wall, reactor vessel air cooling systems employing natural circulation phenomena, unusual fuel elements such as pebbles of different sizes and construction, fluidized bed fuel, exotic coolant such as led-bismuth eutectic for which special equations of state are needed, and accelerator driven systems with unique control features. The combination of new reactor components, fuels and coolants in advanced nuclear power plants require a specific modeling system such as the DSNP. (Dynamic Simulator for Nuclear Power-plants)

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

    Energy Technology Data Exchange (ETDEWEB)

    Miller, M.C.; Tobin, S. [Los Alamos National Laboratory, P.O. Box 1663, MS E540, Los Alamos, NM 87545 (United States); Smith, L.E. [Pacific Northwest National Laboratory (United States); Ehinger, M. [Oak Ridge National Laboratory (United States); Dougan, A. [Lawrence Livermore National Laboratory (United States); Cipiti, B. [Sandia National Laboratory (United States); Bakel, A. [Argonne National Laboratory (United States); Bean, R. [Idaho National Laboratory (United States)

    2008-07-01

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

  13. Cost estimate guidelines for advanced nuclear power technologies

    International Nuclear Information System (INIS)

    Several advanced power plant concepts are currently under development. These include the Modular High Temperature Gas Cooled Reactors, the Advanced Liquid Metal Reactor and the Advanced Light Water Reactors. One measure of the attractiveness of a new concept is its cost. Invariably, the cost of a new type of power plant will be compared with other alternative forms of electrical generation. This report provides a common starting point, whereby the cost estimates for the various power plants to be considered are developed with common assumptions and ground rules. Comparisons can then be made on a consistent basis. This is the second update of these cost estimate guidelines. Changes have been made to make the guidelines more current (January 1, 1992) and in response to suggestions made as a result of the use of the previous report. The principal changes are that the reference site has been changed from a generic Northeast (Middletown) site to a more central site (EPRI's East/West Central site) and that reference bulk commodity prices and labor productivity rates have been added. This report is designed to provide a framework for the preparation and reporting of costs. The cost estimates will consist of the overnight construction cost, the total plant capital cost, the operation and maintenance costs, the fuel costs, decommissioning costs and the power production or busbar generation cost

  14. Recent advances in multifunctional silica-based hybrid nanocarriers for bioimaging and cancer therapy

    Science.gov (United States)

    Lim, Wei Qi; Phua, Soo Zeng Fiona; Xu, Hesheng Victor; Sreejith, Sivaramapanicker; Zhao, Yanli

    2016-06-01

    In recent years, there has been a considerable research focus on integrating cancer cell imaging and therapeutic functions into single nanoscale platforms for better treatment of cancer. This task could often be achieved by incorporating multiple components into a hybrid nanosystem. In this minireview, we highlight different types of silica-based hybrid nanosystems and their recent applications as integrated multifunctional platforms for cancer imaging and treatment. The discussions are divided into several sections focusing on various types of materials employed to integrate with silica, which include silica-metallic nanoparticle based hybrid nanocarriers, silica-gold nanoparticle based hybrid nanocarriers, silica-quantum dot based hybrid nanocarriers, silica-upconversion nanoparticle based hybrid nanocarriers, silica-carbon based hybrid nanocarriers, and organosilica nanocarriers. Therapeutic agents loaded in such hybrids include chemodrugs, proteins, DNA/RNA and photosensitizers. For targeted delivery into tumor sites, targeting ligands such as antibodies, peptides, aptamers, and other small molecules are grafted on the surface of the nanocarriers. At the end of the review, a brief summary and research outlook are presented. This minireview aims to provide a quick update of recent research achievements in the field.

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

    International Nuclear Information System (INIS)

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

  16. 77 FR 34194 - Advance Notification to Native American Tribes of Transportation of Certain Types of Nuclear Waste

    Science.gov (United States)

    2012-06-11

    ... Transportation of Certain Types of Nuclear Waste AGENCY: Nuclear Regulatory Commission. ACTION: Final rule... irradiated reactor fuel and certain nuclear waste passing through or across the boundary of their States... shipment of irradiated reactor fuel and nuclear waste,'' requires licensees to provide advance notice...

  17. Advanced control and instrumentation systems in nuclear power plants. Design, verification and validation

    International Nuclear Information System (INIS)

    The Technical Committee Meeting on design, verification and validation of advanced control and instrumentation systems in nuclear power plants was held in Espoo, Finland on 20 - 23 June 1994. The meeting was organized by the International Atomic Energy Agency's (IAEA) International Working Group's (IWG) on Nuclear Power Plant Control and Instrumentation (NPPCI) and on Advanced Technologies for Water Cooled Reactors (ATWR). VTT Automation together with Imatran Voima Oy and Teollisuuden Voima Oy responded about the practical arrangements of the meeting. In total 96 participants from 21 countries and the Agency took part in the meeting and 34 full papers and 8 posters were presented. Following topics were covered in the papers: (1) experience with advanced and digital systems, (2) safety and reliability analysis, (3) advanced digital systems under development and implementation, (4) verification and validation methods and practices, (5) future development trends. (orig.)

  18. The Westinghouse AP600 -- An update on the advanced simplified nuclear power plant

    International Nuclear Information System (INIS)

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

  19. Key nuclear data measurements for advanced fission energy and white neutron source at CSNS

    International Nuclear Information System (INIS)

    The key nuclear data for advanced fission energy are important in designing advanced nuclear reactors and facilities for nuclear-waste transmutation. Because the present nuclear data library is limited by experimental condition and energy range, the precision of some nuclear data is low, even some nuclear data are blank. In this paper, the status of the nuclear data and white neutron sources were presented. The back-streaming neutron beam at China Spallation Neutron Source (CSNS) has very wide energy spectrum (0.01 eV-200 MeV) and excellent time structure. From the simulation results, it's obtained that the uncollimated neutron fluence rate is around 9.3 × 106 cm-2 · s-1 within the given energy range at 80 m away from the target, which accounts for about 53% of the total neutrons. The time resolution of 0.3%-0.9%, which is important for the Time-of-Flight method, can be obtained for both the parasite operation mode with two proton bunches and the dedicated operation mode with a single proton bunch. CSNS white neutron source will be a good facility for nuclear data measurement. (authors)

  20. Hiberarchy of requirement analysis of reactor protection system for advanced pressurized water reactor nuclear power plant

    International Nuclear Information System (INIS)

    In order to improve the security and the margin of safety of nuclear power plant, the research on requirement analysis of digital reactor protection system for advanced pressurized water reactor nuclear power plant was developed. Based on the known technology, a requirement analysis report was performed. A kind of three-levels pyramidal hierarchy was adopted in the requirement analysis, and the design characteristics of the requirement analysis were described in the analysis report. This hiberarchy can directly illuminate the design characters and logical achievement of the requirement analysis for advanced pressurized water reactor digital protection system. (authors)

  1. Hybrid MSF-RO nuclear desalination demonstration project, Kalpakkam - design of preheat RO system

    International Nuclear Information System (INIS)

    The Nuclear Desalination Demonstration Project (NDDP), Kalpakkam envisages setting up a 6300 m3/d capacity hybrid MSF-RO plant based on the indigenous design. The plant will meet the process water requirements of MAPS and will augment the drinking water sources of the nearby complex. The hybrid design has the following advantages; (i) operation of RO plant using grid electricity during reactor shut down thus increasing the desalination plant availability; (ii) economic production of process water for steam generation for the power station after minor polishing of the product water from MSF plant, (iii) blending the products of MSF and RO plants to make drinking quality water; (iv) to utilize the cooling seawater from the reject stages of MSF plant as feed for the RO plant. This would either increase the RO product output or reduce the operating pressure of RO plant thereby improving the economics. This paper describes the basic process flow sheet of SWRO plant, part of the hybrid MSF-RO desalination plant. The SWRO plant consists of pretreatment system, high pressure pumping system with energy recovery turbine, RO modules and membrane cleaning system. The product water from SWRO plant having TDS of about 400 ppm will be mixed with product water of the MSF plant containing 10 ppm TDS. The projection of the permeate output and TDS for a few SWRO commercial modules at different sea water temperatures are carried out to select the optimum conditions of the SWRO plant. The role of energy recovery from RO reject stream is also investigated. As the seawater TDS at our site is around 35,000 ppm it has been proposed to study the feasibility of using reject stream from RO plant as feed for the MSF plant in future. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2005-03-15

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

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

    International Nuclear Information System (INIS)

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

  4. The nuclear fuel cycle with advanced reactor systems - analysis of its economic fundamentals and possibilities

    International Nuclear Information System (INIS)

    The purpose of the study is to analyse the nuclear fuel cycle of alternative advanced reactor systems with respect to their different mass flows of nuclear fuel and to judge the economic feasibility of these advanced nuclear technologies using a specific fuel cycle model. It is the particular importance of this subject that many technical, physical, political and economic coherences are combined in a very complex manner. A detailed description of the problem is given in the introductional chapter 1. The following chapter 2 gives a sufficient survey of the different techniques and technical facilities of the nuclear fuel cycles in question. Part 3 includes an investigation of logical coherences between typical fuel cycle mass flows which consequently leads to a mathematical model. This model is described in part 4. Chapter 5 then deals with the application of this model by the quantitative estimation and valuation of the economic differences between the conventional and advanced nuclear technology. In the final part of this study the influence of a very important parameter in this context, the price of plutonium, is discussed with respect to the time of introduction of the advanced reactor technology under economic conditions. (orig.)

  5. Basic Research Needs for Advanced Nuclear Systems. Report of the Basic Energy Sciences Workshop on Basic Research Needs for Advanced Nuclear Energy Systems, July 31-August 3, 2006

    Energy Technology Data Exchange (ETDEWEB)

    Roberto, J.; Diaz de la Rubia, T.; Gibala, R.; Zinkle, S.; Miller, J.R.; Pimblott, S.; Burns, C.; Raymond, K.; Grimes, R.; Pasamehmetoglu, K.; Clark, S.; Ewing, R.; Wagner, A.; Yip, S.; Buchanan, M.; Crabtree, G.; Hemminger, J.; Poate, J.; Miller, J.C.; Edelstein, N.; Fitzsimmons, T.; Gruzalski, G.; Michaels, G.; Morss, L.; Peters, M.; Talamini, K.

    2006-10-01

    The global utilization of nuclear energy has come a long way from its humble beginnings in the first sustained nuclear reaction at the University of Chicago in 1942. Today, there are over 440 nuclear reactors in 31 countries producing approximately 16% of the electrical energy used worldwide. In the United States, 104 nuclear reactors currently provide 19% of electrical energy used nationally. The International Atomic Energy Agency projects significant growth in the utilization of nuclear power over the next several decades due to increasing demand for energy and environmental concerns related to emissions from fossil plants. There are 28 new nuclear plants currently under construction including 10 in China, 8 in India, and 4 in Russia. In the United States, there have been notifications to the Nuclear Regulatory Commission of intentions to apply for combined construction and operating licenses for 27 new units over the next decade. The projected growth in nuclear power has focused increasing attention on issues related to the permanent disposal of nuclear waste, the proliferation of nuclear weapons technologies and materials, and the sustainability of a once-through nuclear fuel cycle. In addition, the effective utilization of nuclear power will require continued improvements in nuclear technology, particularly related to safety and efficiency. In all of these areas, the performance of materials and chemical processes under extreme conditions is a limiting factor. The related basic research challenges represent some of the most demanding tests of our fundamental understanding of materials science and chemistry, and they provide significant opportunities for advancing basic science with broad impacts for nuclear reactor materials, fuels, waste forms, and separations techniques. Of particular importance is the role that new nanoscale characterization and computational tools can play in addressing these challenges. These tools, which include DOE synchrotron X

  6. Materials Issues in Advanced Nuclear Systems: Executive Summary of DOE Basic Research Needs Workshop, 'Basic Research Needs for Advanced Nuclear Energy Systems'

    International Nuclear Information System (INIS)

    The global utilization of nuclear energy has come a long way from its humble beginnings in the first sustained nuclear reaction at the University of Chicago in 1942. Today, there are over 440 nuclear reactors in 31 countries producing approximately 16% of the electrical energy used worldwide. In the United States, 104 nuclear reactors currently provide 19% of electrical energy used nationally. The International Atomic Energy Agency projects significant growth in the utilization of nuclear power over the next several decades due to increasing demand for energy and environmental concerns related to emissions from fossil plants. There are 28 new nuclear plants currently under construction including 10 in China, 8 in India, and 4 in Russia. In the United States, there have been notifications to the Nuclear Regulatory Commission of intentions to apply for combined construction and operating licenses for 27 new units over the next decade. The projected growth in nuclear power has focused increasing attention on issues related to the permanent disposal of nuclear waste, the proliferation of nuclear weapons technologies and materials, and the sustainability of a once-through nuclear fuel cycle. In addition, the effective utilization of nuclear power will require continued improvements in nuclear technology, particularly related to safety and efficiency. In all of these areas, the performance of materials and chemical processes under extreme conditions is a limiting factor. The related basic research challenges represent some of the most demanding tests of our fundamental understanding of materials science and chemistry, and they provide significant opportunities for advancing basic science with broad impacts for nuclear reactor materials, fuels, waste forms, and separations techniques. Of particular importance is the role that new nanoscale characterization and computational tools can play in addressing these challenges. These tools, which include DOE synchrotron X

  7. Advances in chemical standards for nuclear fuel analysis and safeguards purposes

    International Nuclear Information System (INIS)

    The objectives of the Consultants' Meeting were to evaluate the results of enquiries conducted by the IAEA and the CEC on the needs and availability of nuclear reference materials, to prepare a report on the results of the enquiries and on the advances in chemical standards for nuclear fuel analyses and safeguards purposes and to identify needs which are not being met or could not be met in the future

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

    International Nuclear Information System (INIS)

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

  9. Neutron reaction cross section data for advanced nuclear applications

    International Nuclear Information System (INIS)

    Full text of publication follows: Worldwide major research efforts are currently being carried out in order to develop a new concept of nuclear power generation, so-called accelerator driven systems (ADS) for energy production and transmutation of radioactive nuclear waste. A suggested approach is the energy amplifier (EA), which is a sub-critical reactor using a powerful proton accelerator and a spallation reaction as neutron source. Since the EA is based on the thorium-uranium fuel cycle, where the natural resources of the main fuel thorium are estimated to last for hundred thousands of years, it is considered to provide clean and almost inexhaustible nuclear energy. Apart from necessary new technical developments, the realization of these concepts depends strongly on the availability of accurate nuclear reaction data. In particular, precise knowledge about cross sections for fission, neutron capture and scattering is required for the nuclides involved in the Th-U fuel cycle. Among the first priority isotopes the IAEA had pointed out 231Pa and 233Pa. The latter one, 233Pa, is of specific interest, since it plays an important role as an intermediate nucleus in the formation of the fissile 233U from the fertile 232Th. With its half life of 27.0 days for β-decay, 233Pa is not a 'long-lived' nucleus, but it still requires careful attention in the design and operation of thorium-fueled reactors. When a thorium-fueled reactor is stopped, the present amount of 233Pa will continue to decay into 233U, leading to an increase in reactivity, which may even cause criticality. This mechanism is known as 'protactinium effect' and is proportional to the power level of the reactor. Also the precise knowledge of the fission cross section of 231Pa (above 1 b for fast neutrons) is essential for simulations of the balance of nuclei in and, thus, the reactivity behavior of the reactor. We present recent cross section data from direct, energy resolved measurements of the neutron

  10. Nuclear design report for system-integrated modular advanced reactor

    Energy Technology Data Exchange (ETDEWEB)

    Park, Sang Yoon; Lee, Chung Chan; Zee, Sung Quun; Chang, Moon Hee [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2002-02-01

    This report presents nuclear characteristics analysis results for SMART. Information is given on fuel loading, power density distributions, reactivity coefficients and control rod worths. The core consists of 57 modified Korean Standard Fuel Assemblies (m-KOFAs). and all fuel assemblies contain burnable absorbers to control the power distribution and the excess reactivity that is required for soluble boron-free and ultra longer cycle operation. The cycle length of SMART amounts to 990 EFPD corresponding to a cycle burnup of 26,160 MWD/MTU. 4 refs., 92 figs., 5 tabs. (Author)

  11. Advanced maintenance, inspection & repair technology for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hinton, B.M.

    1994-12-31

    Maintenance, inspection, and repair technology for nuclear power plants is outlined. The following topics are discussed: technology for reactor systems, reactor refueling bridge, fuel inspection system, fuel shuffling software, fuel reconstitution, CEA/RCCA/CRA inspection, vessel inspection capabilities, CRDM inspection and repair, reactor internals inspection and repair, stud tensioning system, stud/nut cleaning system, EDM machining technology, MI Cable systems, core exit T/C nozzle assemblies, technology for steam generators, genesis manipulator systems, ECT, UT penetrant inspections, steam generator repair and cleaning systems, technology for balance of plant, heat exchangers, piping and weld inspections, and turbogenerators.

  12. Influence of nuclear data uncertainties on thorium fusion-fission hybrid blanket nucleonic performance

    Energy Technology Data Exchange (ETDEWEB)

    Cheng, E.T.; Mathews, D.R.

    1979-09-01

    The fusion-fission hybrid blanket proposed for the Tandem Mirror Hybrid Reactor employs thorium metal as the fertile material. Based on the ENDF/B-IV nuclear data, the /sup 233/U and tritium production rate and blanket energy multiplication averaged over the blanket lifetime of about 9 MW-yr/m/sup 2/ are 0.76 and 1.12 per D-T neutron and 4.8, respectively. At the time of the blanket discharge, the /sup 233/U enrichment in the thorium metal is about 3%. The thorium cross sections given by the ENDF/B-IV and V were reviewed, and the important partial cross sections such as (n,2n), (n,3n), and (n,..gamma..) were found to be known to +-10 to 20% in the respective energy range of interest. A sensitivity study showed that the /sup 233/U and tritium production rate and blanket energy multiplication are relatively sensitive to the thorium capture and fission cross section uncertainties. In order to predict the above parameters within +-1%, the Th(n,..gamma..) and Th(n,..nu..f) cross sections must be measured within about +-2% in the energy range 3 to 3000 keV and 13.5 to 15 MeV, respectively.

  13. Influence of nuclear data uncertainties on thorium fusion-fission hybrid blanket nucleonic performance

    International Nuclear Information System (INIS)

    The fusion-fission hybrid blanket proposed for the Tandem Mirror Hybrid Reactor employs thorium metal as the fertile material. Based on the ENDF/B-IV nuclear data, the 233U and tritium production rate and blanket energy multiplication averaged over the blanket lifetime of about 9 MW-yr/m2 are 0.76 and 1.12 per D-T neutron and 4.8, respectively. At the time of the blanket discharge, the 233U enrichment in the thorium metal is about 3%. The thorium cross sections given by the ENDF/B-IV and V were reviewed, and the important partial cross sections such as (n,2n), (n,3n), and (n,γ) were found to be known to +-10 to 20% in the respective energy range of interest. A sensitivity study showed that the 233U and tritium production rate and blanket energy multiplication are relatively sensitive to the thorium capture and fission cross section uncertainties. In order to predict the above parameters within +-1%, the Th(n,γ) and Th(n,νf) cross sections must be measured within about +-2% in the energy range 3 to 3000 keV and 13.5 to 15 MeV, respectively

  14. Radiation and physical protection challenges at advanced nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Full text: The purpose of this study is to examine challenges and opportunities for radiation protection in advanced nuclear reactors and fuel facilities proposed under the Generation IV (GEN IV) initiative which is examining and pursuing the exploration and development of advanced nuclear science and technology; and the Global Nuclear Energy Partnership (GNEP), which seeks to develop worldwide consensus on enabling expanded use of economical, carbon-free nuclear energy to meet growing energy demand. The International Energy Agency projects nuclear power to increase at a rate of 1.3 to 1.5 percent a year over the next 20 years, depending on economic growth. Much of this growth will be in Asia, which, as a whole, currently has plans for 40 new nuclear power plants. Given this increase in demand for new nuclear power facilities, ranging from light water reactors to advanced fuel processing and fabrication facilities, it is necessary for radiation protection and physical protection technologies to keep pace to ensure both worker and public health. This paper is based on a review of current initiatives and the proposed reactors and facilities, primarily the nuclear fuel cycle facilities proposed under the GEN IV and GNEP initiatives. Drawing on the Technology Road map developed under GEN IV, this work examines the potential radiation detection and protection challenges and issues at advanced reactors, including thermal neutron spectrum systems, fast neutron spectrum systems and nuclear fuel recycle facilities. The thermal neutron systems look to improve the efficiency of production of hydrogen or electricity, while the fast neutron systems aim to enable more effective management of actinides through recycling of most components in the discharged fuel. While there are components of these advanced systems that can draw on the current and well-developed radiation protection practices, there will inevitably be opportunities to improve the overall quality of radiation

  15. Progress of nuclear safety for symbiosis and sustainability advanced digital instrumentation, control and information systems for nuclear power plants

    CERN Document Server

    Yoshikawa, Hidekazu

    2014-01-01

    This book introduces advanced methods of computational and information systems allowing readers to better understand the state-of-the-art design and implementation technology needed to maintain and enhance the safe operation of nuclear power plants. The subjects dealt with in the book are (i) Full digital instrumentation and control systems and human?machine interface technologies (ii) Risk? monitoring methods for large and? complex? plants (iii) Condition monitors for plant components (iv) Virtual and augmented reality for nuclear power plants and (v) Software reliability verification and val

  16. Mobile hybrid (nuclear/oil fired) gas turbine cogeneration power plant concept

    International Nuclear Information System (INIS)

    A small mobile hybrid nuclear/oil-fired cogeneration power plant is proposed, its prime function being to provide power and heat to users in isolated areas (e.g. polar regions, islands, deserts) and for emergency use, for example in natural disaster areas where fuel supply logistic concerns are a major problem. The power plant would consist of five basic modules which would be skid-mounted for air or truck transportation to the site. A duplicity of heat sources is inherent in the design concept, i.e. a small helium-cooled nuclear reactor and an industrial gas turbine with an external combustor. Initial operation would be with the combustion gas turbine which could burn a variety of liquid fuels, including diesel oil, jet fuel, kerosene, gasoline, etc. Two factors would be dominant in the plant design, i.e. safety and reliability considerations. Multiple metallic barriers and independent loops between the reactor and the prime-mover facilitate the use of a conventional open cycle industrial gas turbine generator. The reactor embodies passive cooling capability and is of a second generation inherently safe type. Should it be necessary, the ease of module removal and replacement would assure high availability. The proposed power plant is based on proven and available technology. The plant can be operated in regions where cooling water is not available; however, if a source is available, the cogeneration module would provide process heat (e.g. hot water, steam, hot air) or be used for desalination. The proposed power plant concept, by its hybrid nature, is component intensive, and in the conventional sense could not be justified on an economic basis and, of course, is not intended for commercial power generation service, but is rather aimed at meeting the needs of users who have no indigenous fuel supply and where fuel supply logistics are extremely difficult. (Copyright (c) 1998 Elsevier Science B.V., Amsterdam. All rights reserved.)

  17. Clinical applications of SPECT/CT: New hybrid nuclear medicine imaging system

    International Nuclear Information System (INIS)

    Interest in multimodality imaging shows no sign of subsiding. New tracers are spreading out the spectrum of clinical applications and innovative technological solutions are preparing the way for yet more modality marriages: hybrid imaging. Single photon emission computed tomography (SPECT) has enabled the evaluation of disease processes based on functional and metabolic information of organs and cells. Integration of X ray computed tomography (CT) into SPECT has recently emerged as a brilliant diagnostic tool in medical imaging, where anatomical details may delineate functional and metabolic information. SPECT/CT has proven to be valuable in oncology. For example, in the case of a patient with metastatic thyroid cancer, neither SPECT nor CT alone could identify the site of malignancy. SPECT/CT, a hybrid image, precisely identified where the surgeon should operate. However SPECT/CT is not just advantageous in oncology. It may also be used as a one-stop-shop for various diseases. Clinical applications with SPECT/CT have started and expanded in developed countries. It has been reported that moving from SPECT alone to SPECT/CT could change diagnoses in 30% of cases. Large numbers of people could therefore benefit from this shift all over the world. This report presents an overview of clinical applications of SPECT/CT and a relevant source of information for nuclear medicine physicians, radiologists and clinical practitioners. This information may also be useful for decision making when allocating resources dedicated to the health care system, a critical issue that is especially important for the development of nuclear medicine in developing countries. In this regard, the IAEA may be heavily involved in the promotion of programmes aimed at the IAEA's coordinated research projects and Technical Cooperation projects

  18. Launch Vehicles Based on Advanced Hybrid Rocket Motors: An Enabling Technology for the Commercial Small and Micro Satellite Planetary Science

    Science.gov (United States)

    Karabeyoglu, Arif; Tuncer, Onur; Inalhan, Gokhan

    2016-07-01

    Mankind is relient on chemical propulsion systems for space access. Nevertheless, this has been a stagnant area in terms of technological development and the technology base has not changed much almost for the past forty years. This poses a vicious circle for launch applications such that high launch costs constrain the demand and low launch freqencies drive costs higher. This also has been a key limiting factor for small and micro satellites that are geared towards planetary science. Rather this be because of the launch frequencies or the costs, the access of small and micro satellites to orbit has been limited. With today's technology it is not possible to escape this circle. However the emergence of cost effective and high performance propulsion systems such as advanced hybrid rockets can decrease launch costs by almost an order or magnitude. This paper briefly introduces the timeline and research challenges that were overcome during the development of advanced hybrid LOX/paraffin based rockets. Experimental studies demonstrated effectiveness of these advanced hybrid rockets which incorporate fast burning parafin based fuels, advanced yet simple internal balistic design and carbon composite winding/fuel casting technology that enables the rocket motor to be built from inside out. A feasibility scenario is studied using these rocket motors as building blocks for a modular launch vehicle capable of delivering micro satellites into low earth orbit. In addition, the building block rocket motor can be used further solar system missions providing the ability to do standalone small and micro satellite missions to planets within the solar system. This enabling technology therefore offers a viable alternative in order to escape the viscous that has plagued the space launch industry and that has limited the small and micro satellite delivery for planetary science.

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

    Energy Technology Data Exchange (ETDEWEB)

    Donald D Dudenhoeffer; Burce P Hallbert

    2007-03-01

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

  20. Development and utilization of the NRC policy statement on the regulation of advanced nuclear power plants

    International Nuclear Information System (INIS)

    On March 26, 1985, the US Nuclear Regulatory Commission issued for public comment a ''Proposed Policy for Regulation of Advanced Nuclear Power Plants'' (50 FR 11884). This report presents and discusses the Commission's final version of that policy as titled and published on July 8, 1986 ''Regulation of Advanced Nuclear Power Plants, Statement of Policy'' (51 FR 24643). It provides an overview of comments received from the public, of the significant changes from the proposed Policy Statement to the final Policy Statement, and of the Commission's response to six questions contained in the proposed Policy Statement. The report also discusses the definition for advanced reactors, the establishment of an Advanced Reactors Group, the staff review approach and information needs, and the utilization of the Policy Statement in relation to other NRC programs, including the policies for safety goals, severe accidents and standardization. In addition, guidance for advanced reactors with respect to operating experience, technology development, foreign information and data, and prototype testing is provided. Finally, a discussion on the use of less prescriptive and nonprescriptive design criteria for advanced reactors, which the Policy Statement encourages, is presented

  1. Accelerated development of advanced steels for nuclear applications

    International Nuclear Information System (INIS)

    Significant progress has been achieved in the operational performance and radiation resistance of ferritic-martensitic steels during the past few decades. Conventional high temperature steels, such as HT-9 and 2 1/4 Cr-1Mo have evolved into super Oxide Dispersion Strengthened (ODS) steels through successive optimization to meet strict performance and radiation-resistance constraints. Such evolution was possible through a combination of experimentation, modeling and empirical information. Further development and optimization of structural steels in nuclear applications will require full utilization of the available array of sophisticated experimental techniques and multiscale computational modeling, in addition to empirical data. We present here a systematic approach to the process of optimum steel development, by linking material fabrication to thermo-mechanical properties through a physical understanding of microstructure evolution. The optimization process is based on the application of design constraints (e.g. low activation, low DBTT, low swelling, creep resistance, and weldability) to describe the required microstructures, which in turn, can be controlled through material processing techniques. Prospects for future design of optimum structural steels in nuclear applications by utilization of the hierarchy of multiscale experimental and computational strategies will be described. (author)

  2. Design of radiation resistant metallic multilayers for advanced nuclear systems

    Energy Technology Data Exchange (ETDEWEB)

    Zhernenkov, Mikhail, E-mail: zherne@bnl.gov, E-mail: gills@bnl.gov; Gill, Simerjeet, E-mail: zherne@bnl.gov, E-mail: gills@bnl.gov; Stanic, Vesna; DiMasi, Elaine; Kisslinger, Kim; Ecker, Lynne [Brookhaven National Laboratory, Upton, New York 11973 (United States); Baldwin, J. Kevin; Misra, Amit [Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States); Demkowicz, M. J. [Department of Materials Science and Engineering, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States)

    2014-06-16

    Helium implantation from transmutation reactions is a major cause of embrittlement and dimensional instability of structural components in nuclear energy systems. Development of novel materials with improved radiation resistance, which is of the utmost importance for progress in nuclear energy, requires guidelines to arrive at favorable parameters more efficiently. Here, we present a methodology that can be used for the design of radiation tolerant materials. We used synchrotron X-ray reflectivity to nondestructively study radiation effects at buried interfaces and measure swelling induced by He implantation in Cu/Nb multilayers. The results, supported by transmission electron microscopy, show a direct correlation between reduced swelling in nanoscale multilayers and increased interface area per unit volume, consistent with helium storage in Cu/Nb interfaces in forms that minimize dimensional changes. In addition, for Cu/Nb layers, a linear relationship is demonstrated between the measured depth-dependent swelling and implanted He density from simulations, making the reflectivity technique a powerful tool for heuristic material design.

  3. Recent advances in nuclear fuels technology for thermal reactors

    International Nuclear Information System (INIS)

    In today's competitive electrical generation, many nuclear power generators are lowering operating and fuel cycle costs by extending burnups, utilizing longer cycles, reducing outage duration, increasing peaking factors for more efficient fuel management; and by up rating to maximize energy output from the reactors. To better equip nuclear operators to meet these competitive challenges, Westinghouse has strategically aligned its goals to ensure that customer needs are met and that fuel supplied operates flawlessly. Westinghouse's fuel performance program implements design features and manufacturing processes to maximize margins to failure, specify bounds of reactor operation, and monitor critical operating parameters using BEACON software as well as specify and implement a robust Post Irradiation Examination (PIE) to obtain early feedback on fuel performance. Westinghouse's unwavering commitment to achieve flawless fuel performance and to innovate resulted in exceptional pressurized water reactor (PWR), boiling water reactor (BWR), and VVER fuel performance worldwide. This paper covers decades of continuous innovation in fuel design and manufacturing process which supports our outstanding fuel performance in all LWR fuel types. This paper also includes information about Westinghouse's state-of-the-art tools and methodologies utilized to improve fuel performance as well as recent developments in fuel cladding material. (author)

  4. Advances in nuclear fuel cycle materials and concepts. Vol. 1

    International Nuclear Information System (INIS)

    This presentation gives an overview of the new trends in the materials used in various steps of the nuclear fuel cycle. This will cover fuels for various types of reactors (PWRs, HTRs, ... etc.) cladding materials, control rod materials, reactor structural materials, as well as materials used in the back end of the fuel cycle. Problems associated with corrosion of fuel cladding materials as well as those in control rod materials (B4 C swelling...etc.), and approaches for combating these influences are reviewed. For the case of reactor pressure vessel materials issues related to the influences of alloy composition, design approaches including the use of more forged parts and minimizing, as for as possible, longitudinal welds especially in the central region, are discussed. Furthermore the application of techniques for recovery of pre-irradiation mechanical properties of PVS components is also covered. New candidate materials for the construction of high level waste containers including modified types of stainless steel (high Ni and high MO), nickel-base alloys and titanium alloys are also detailed. Finally, nuclear fuel cycle concepts involving plutonium and actinides recycling shall be reviewed. 28 figs., 6 tabs

  5. Research and development of nuclear advanced robot system

    International Nuclear Information System (INIS)

    In the large scale project 'Robots for severity limit works' of Agency of Industrial Science and Technology, Ministry of International Trade and Industry, the research and development have been carried out for eight years since 1983 for the working robots in the fields of nuclear power, ocean and fire fighting. In this report, the technical results of the development aiming at the movable, versatile robot which possesses the high capability of remote operation supported by autonomy, and can carry out the maintenance of the various machinery and equipment arranged in narrow and complicated state in nuclear power plants in place of workers, are described. For this purpose, ten manufacturers related to atomic energy organized the technical research association, and jointly developed from elementary technologies to system technology. The whole robot system, the specification of the robot, the computer system and the control and operation performance are reported. The main results of technical development such as four-leg walking, manipulation technology, visual information processing and operation system, communication and support technologies and wall surface moving mechanism are described. (K.I.)

  6. Cladding and Structural Materials for Advanced Nuclear Energy Systems

    Energy Technology Data Exchange (ETDEWEB)

    Was, G S; Allen, T R; Ila, D; C,; Levi,; Morgan, D; Motta, A; Wang, L; Wirth, B

    2011-06-30

    The goal of this consortium is to address key materials issues in the most promising advanced reactor concepts that have yet to be resolved or that are beyond the existing experience base of dose or burnup. The research program consists of three major thrusts: 1) high-dose radiation stability of advanced fast reactor fuel cladding alloys, 2) irradiation creep at high temperature, and 3) innovative cladding concepts embodying functionally-graded barrier materials. This NERI-Consortium final report represents the collective efforts of a large number of individuals over a period of three and a half years and included 9 PIs, 4 scientists, 3 post-docs and 12 students from the seven participating institutions and 8 partners from 5 national laboratories and 3 industrial institutions (see table). University participants met semi-annually and participants and partners met annually for meetings lasting 2-3 days and designed to disseminate and discuss results, update partners, address outstanding issues and maintain focus and direction toward achieving the objectives of the program. The participants felt that this was a highly successful program to address broader issues that can only be done by the assembly of a range of talent and capabilities at a more substantial funding level than the traditional NERI or NEUP grant. As evidence of the success, this group, collectively, has published 20 articles in archival journals and made 57 presentations at international conferences on the results of this consortium.

  7. Optimization of the hybrid sulfur cycle for nuclear hydrogen production using UniSim Design

    International Nuclear Information System (INIS)

    the improvement of the electrolysis, development of the structural materials and the effective utilization of the high temperature nuclear heat for the high temperature, high acid concentration environment. The pressure effect on the capital cost as well as on the cycle efficiency should be evaluated simultaneously. In the simulation environment, together with much simpler data management method, the more detailed and realistic flow sheet is expected to give us a chance to explore the possibility of the nuclear energy aided hybrid sulfur cycle as a hydrogen production method. (author)

  8. A study on advanced man-machine interface system for autonomous nuclear power plants

    International Nuclear Information System (INIS)

    A man-machine interface(MMI) system of an autonomous nuclear power plant has an advanced function compared with that of the present nuclear power plants. The MMI has a function model of a plant state, and updates and revises this function model by itself. This paper describes the concept of autonomous nuclear power plants, a plant simulator of an autonomous power plant, a contracted function model of a plant state, three-dimensional color graphic display of a plant state, and an event-tree like expression for plant states. (author)

  9. Measurements of neutron cross sections for advanced nuclear energy systems at n_TOF (CERN

    Directory of Open Access Journals (Sweden)

    Barbagallo M.

    2014-03-01

    Full Text Available The n_TOF facility operates at CERN with the aim of addressing the request of high accuracy nuclear data for advanced nuclear energy systems as well as for nuclear astrophysics. Thanks to the features of the neutron beam, important results have been obtained on neutron induced fission and capture cross sections of U, Pu and minor actinides. Recently the construction of another beam line has started; the new line will be complementary to the first one, allowing to further extend the experimental program foreseen for next measurement campaigns.

  10. Use of molecular nuclear methods in communicable diseases: From nucleic acid hybridization to proteomics

    International Nuclear Information System (INIS)

    In spite of decades of intensive research on communicable diseases, infection agents still remain a major cause of morbidity and mortality in humans. These rates have driven a major resurgence in biological research efforts for the identification of new targets for vaccine development, drugs and diagnostics assays products. Molecular nuclear techniques focused in nucleic acid hybridization and DNA amplification and more recently proteomic approaches are employed to address questions related to communicable diseases. In nucleic acid hybridization, denatured DNA or RNA is immobilized on an inert support, so that bound sequences are available for hybridization with an added nucleic acid radioactive probe to facilitate analysis. After extensive washing, hybrids are detected by autoradiography or phosphoimager analyzer. Polymerase chain reaction (PCR), is a very sensitive method for nucleic acid amplification used when the targets are scarce in the cells or in clinical material. Differently, the challenge of proteome analysis lies with the task of achieving a combination of high-throughput screening while maintaining high sensitivity for the detection of low copy number proteins. Many different detection technologies have been developed to improve visualization of proteins in protein analysis and radiolabelling is one of the strategies for protein detection. For metabolic experiments, proteins must be labelled with an appropriate radioactive isotope in vivo prior to isolation by electrophoretic analysis. Additionally, protein phosphorylation, an important post-translational modification, is analyzed by using 32P for in vivo labelling of phosphorylated proteins and further identification by mass spectrometry. The major problems which limit proteomic studies deal with the comparative analysis of 2DE gel images. In conventional methodology, the protein samples to be compared are separated independently on different gels. Using a 2DE image analysis software spots are

  11. Nuclear plants control: towards an more advanced automation

    International Nuclear Information System (INIS)

    Reactor operation appears to have a lower automation level than other fields of production industry. Compiled data point out that human factors are implied in about 70 % of un acceptable errors happening in a nuclear plant. But no obvious conclusion can result from these data. Human factor are so numerous and unlike that no mathematical model can be achieved. For instance, instead of assuming a whole automated control, a computerized aided control system can lower human faults probability by lowering attention requirements and hence fatigue. Man-machine system engineering and interactive display devices appear to be the best tools to determine the optimal automation level for the highest safety level. CEA and EDF use them in their ''ESCRIME'' coordinated research program. (D.L.)

  12. Nanostructured Fe-Cr Alloys for Advanced Nuclear Energy Applications

    Energy Technology Data Exchange (ETDEWEB)

    Scattergood, Ronald O. [North Carolina State Univ., Raleigh, NC (United States)

    2016-04-26

    We have completed research on the grain-size stabilization of model nanostructured Fe14Cr base alloys at high temperatures by the addition of non-equilibrium solutes. Fe14Cr base alloys are representative for nuclear reactor applications. The neutron flux in a nuclear reactor will generate He atoms that coalesce to form He bubbles. These can lead to premature failure of the reactor components, limiting their lifetime and increasing the cost and capacity for power generation. In order to mitigate such failures, Fe14Cr base alloys have been processed to contain very small nano-size oxide particles (less than 10 nm in size) that trap He atoms and reduce bubble formation. Theoretical and experimental results indicate that the grain boundaries can also be very effective traps for He atoms and bubble formation. An optimum grain size will be less than 100 nm, ie., nanocrystalline alloys must be used. Powder metallurgy methods based on high-energy ball milling can produce Fe-Cr base nanocrystalline alloys that are suitable for nuclear energy applications. The problem with nanocrystalline alloys is that excess grain-boundary energy will cause grains to grow at higher temperatures and their propensity for He trapping will be lost. The nano-size oxide particles in current generation nuclear alloys provide some grain size stabilization by reducing grain-boundary mobility (Zener pinning – a kinetic effect). However the current mitigation strategy minimizing bubble formation is based primarily on He trapping by nano-size oxide particles. An alternate approach to nanoscale grain size stabilization has been proposed. This is based on the addition of small amounts of atoms that are large compared to the base alloy. At higher temperatures these will diffuse to the grain boundaries and will produce an equilibrium state for the grain size at higher temperatures (thermodynamic stabilization – an equilibrium effect). This would be preferred compared to a kinetic effect, which is not

  13. Advancing Nuclear Physics Through TOPS Solvers and Tools

    CERN Document Server

    Ng, E; Wild, S M; Munson, T; Aktulga, H; Yang, C; Maris, P; Vary, J P; Schunck, N; Bertolli, M G; Kortelainen, M; Nazarewicz, W; Papenbrock, T; Stoitsov, M V

    2011-01-01

    At the heart of many scientific applications is the solution of algebraic systems, such as linear systems of equations, eigenvalue problems, and optimization problems, to name a few. TOPS, which stands for Towards Optimal Petascale Simulations, is a SciDAC applied math center focused on the development of solvers for tackling these algebraic systems, as well as the deployment of such technologies in large-scale scientific applications of interest to the U.S. Department of Energy. In this paper, we highlight some of the solver technologies we have developed in optimization and matrix computations. We also describe some accomplishments achieved using these technologies in UNEDF, a SciDAC application project on nuclear physics.

  14. Advances in fluid inclusion analysis using the nuclear microprobe

    International Nuclear Information System (INIS)

    The steady development, since 1987, of nuclear microprobe methods for in situ, non-destructive fluid inclusion analysis has resulted in techniques for standardless, quantitative analysis of individual fluid inclusions in minerals. These techniques offer detection sensitivities of around 20-50 ppm in the fluid using PIXE, in a short analysis time, and provide simultaneous multi-element data. PIXE is complemented by γ-ray analysis using PIGE, which provides a useful, simultaneous light element (Li, B, F, Na, Mg, Al) detection capability, and by H recoil analysis using ERDA. These techniques have been used to tackle problems in a range of geological environments, and have yielded unique insight into ore forming processes in magmatic-hydrothermal systems

  15. Advances in fluid inclusion analysis using the nuclear microprobe

    Energy Technology Data Exchange (ETDEWEB)

    Ryan, Chris E-mail: c.ryan@syd.dem.csiro.au

    1999-09-02

    The steady development, since 1987, of nuclear microprobe methods for in situ, non-destructive fluid inclusion analysis has resulted in techniques for standardless, quantitative analysis of individual fluid inclusions in minerals. These techniques offer detection sensitivities of around 20-50 ppm in the fluid using PIXE, in a short analysis time, and provide simultaneous multi-element data. PIXE is complemented by {gamma}-ray analysis using PIGE, which provides a useful, simultaneous light element (Li, B, F, Na, Mg, Al) detection capability, and by H recoil analysis using ERDA. These techniques have been used to tackle problems in a range of geological environments, and have yielded unique insight into ore forming processes in magmatic-hydrothermal systems.

  16. Advanced nuclear fuel cycle. Optimization by recycling instructive elements

    International Nuclear Information System (INIS)

    Rare-metals and rare-earths produced by fission reaction of uranium 235 in nuclear reactors and consequently contained in spent fuels are considered as potential resources for strategic material in many fields of recent industry. The report consists of several contributed papers concerning with possible utility of such fission products as ruthenium, rhodium, palladium, technetium, and neodymium, and with their recovery and separation from spent fuels as well as possible utilization of actinides and long-lived radioactive elements as radiation sources. To conclude, the present report proposes a new national strategy study to reorient the present scheme of reprocessing of spent fuels and radioactive waste disposal from a new perspective. (S. Ohno)

  17. Advanced scheme for high-yield laser driven nuclear reactions

    Czech Academy of Sciences Publication Activity Database

    Margarone, Daniele; Picciotto, A.; Velyhan, Andriy; Krása, Josef; Kucharik, M.; Mangione, A.; Szydlowsky, A.; Malinowska, A.; Bertuccio, G.; Shi, Y.; Crivellari, M.; Ullschmied, Jiří; Bellutti, P.; Korn, Georg

    2015-01-01

    Roč. 57, č. 1 (2015), 014030. ISSN 0741-3335 R&D Projects: GA MŠk ED1.1.00/02.0061; GA MŠk EE2.3.20.0279 Grant ostatní: ELI Beamlines(XE) CZ.1.05/1.1.00/02.0061; LaserZdroj (OP VK 3)(XE) CZ.1.07/2.3.00/20.0279; FP7(XE) 284464 Institutional research plan: CEZ:AV0Z2043910 Institutional support: RVO:68378271 ; RVO:61389021 Keywords : laser plasma * nuclear reaction * laser fusion Subject RIV: BL - Plasma and Gas Discharge Physics; BH - Optics, Masers, Lasers (UFP-V) Impact factor: 2.186, year: 2014

  18. Advanced surveillance of resistance temperature detectors in nuclear power plants

    International Nuclear Information System (INIS)

    The dynamic response of several RTDs located at the cold leg of a PWR has been studied. A theoretical model for the heat transfer between the RTDs and the surrounding fluid is derived. It proposes a two real poles transfer function. By means of noise analysis techniques in the time domain (autoregressive models) and the Dynamic Data System methodology, the two time constants of the system can be found. A Monte Carlo simulation is performed in order to choose the proper sampling time to obtain both constants. The two poles are found and they permit an advance in situ surveillance of the sensor response time and the sensor dynamics performance. One of the poles is related to the inner dynamics whereas the other one is linked to the process and the inner dynamics. So surveillance on the process and on the inner dynamics can be distinguished. (author)

  19. Advanced communication methods developed for nuclear data communication applications

    International Nuclear Information System (INIS)

    We conducted various experiments and tested data communications methods that may be useful for various applications in nuclear industries. We explored the following areas. I. Scientific data communication among scientists within the laboratory and inter-laboratory data exchange. 2.Data from sensors from remote and wired sensors. 3.Data from multiple sensors with small zone. 4.Data from single or multiple sensors from distances above 100 m and less than 10 km. No any single data communication method was found to be the best solution for nuclear applications and multiple modes of communication were found to be advantageous than any single mode of data communication. Network of computers in the control room and in between laboratories connected with optical fiber or an isolated Ethernet coaxial LAN was found to be optimum. Information from multiple analog process sensors in smaller zones like reactor building and laboratories on 12C LAN and short-range wireless LAN were found to be advantageous. Within the laboratory sensor data network of 12C was found to be cost effective and wireless LAN was comparatively expansive. Within a room infrared optical LAN and FSK wireless LAN were found to be highly useful in making the sensors free from wires. Direct sensor interface on FSK wireless link were found to be fast accurate, cost effective over large distance data communication. Such links are the only way to communicate from sea boy and balloons hardware. 1-wire communication network of Dallas Semiconductor USA for weather station data communication Computer to computer communication using optical LAN links has been tried, temperature pressure, humidity, ionizing radiation, generator RPM and voltage and various other analog signals were also transported o FSK optical and wireless links. Multiple sensors needed a dedicated data acquisition system and wireless LAN for data telemetry. (author)

  20. A Path Forward to Advanced Nuclear Fuels: Spectroscopic Calorimetry of Nuclear Fuel Materials

    International Nuclear Information System (INIS)

    The goal is to relieve the shortage of thermodynamic and kinetic information concerning the stability of nuclear fuel alloys. Past studies of the ternary nuclear fuel UPuZr have demonstrated constituent redistribution when irradiated or with thermal treatment. Thermodynamic data is key to predicting the possibilities of effects such as constituent redistribution within the fuel rods and interaction with cladding materials

  1. 2. JAPAN-IAEA workshop on advanced safeguards technology for the future nuclear fuel cycle. Abstracts

    International Nuclear Information System (INIS)

    This international workshop addressed issues and technologies associated with safeguarding the future nuclear fuel cycle. The workshop discussed issues of interest to the safeguards community, facility operators and State Systems of accounting and control of nuclear materials. Topic areas covered were as follows: Current Status and Future Prospects of Developing Safeguards Technologies for Nuclear Fuel Cycle Facilities, Technology and Instrumentation Needs, Advanced Safeguards Technologies, Guidelines on Developing Instrumentation to Lead the Way for Implementing Future Safeguards, and Experiences and Lessons learned. This workshop was of interest to individuals and organizations concerned with future nuclear fuel cycle technical developments and safeguards technologies. This includes representatives from the nuclear industry, R and D organizations, safeguards inspectorates, State systems of accountancy and control, and Member States Support Programmes

  2. Advanced Educational Methodology on Nuclear Control for Establishment of International Training Center

    International Nuclear Information System (INIS)

    In accordance with the Notice of Ministry of Education, Science and Technology(MEST), KINAC has carried out compulsory education for domestic inspectors, nuclear operators and R and D project managers on nuclear fuel cycle. In addition, as a part of Korea President's declaration at 1st International Nuclear Security Summit Conference, KINAC has to establish an International Training Center(ITC) to increase mutual cooperation among Member States as well as to strengthen their capabilities for effectively coping with current nuclear threats. Along with this, this paper suggests an advanced educational methodology to develop international training course on nuclear control as well as to contribute to effectively ensure human resource in developing countries

  3. A study on optimization of hybrid drive train using Advanced Vehicle Simulator (ADVISOR)

    Science.gov (United States)

    Same, Adam; Stipe, Alex; Grossman, David; Park, Jae Wan

    This study investigates the advantages and disadvantages of three hybrid drive train configurations: series, parallel, and "through-the-ground" parallel. Power flow simulations are conducted with the MATLAB/Simulink-based software ADVISOR. These simulations are then applied in an application for the UC Davis SAE Formula Hybrid vehicle. ADVISOR performs simulation calculations for vehicle position using a combined backward/forward method. These simulations are used to study how efficiency and agility are affected by the motor, fuel converter, and hybrid configuration. Three different vehicle models are developed to optimize the drive train of a vehicle for three stages of the SAE Formula Hybrid competition: autocross, endurance, and acceleration. Input cycles are created based on rough estimates of track geometry. The output from these ADVISOR simulations is a series of plots of velocity profile and energy storage State of Charge that provide a good estimate of how the Formula Hybrid vehicle will perform on the given course. The most noticeable discrepancy between the input cycle and the actual velocity profile of the vehicle occurs during deceleration. A weighted ranking system is developed to organize the simulation results and to determine the best drive train configuration for the Formula Hybrid vehicle. Results show that the through-the-ground parallel configuration with front-mounted motors achieves an optimal balance of efficiency, simplicity, and cost. ADVISOR is proven to be a useful tool for vehicle power train design for the SAE Formula Hybrid competition. This vehicle model based on ADVISOR simulation is applicable to various studies concerning performance and efficiency of hybrid drive trains.

  4. Study on fusion-fission hybrid reactor for transmutation of nuclear waste

    International Nuclear Information System (INIS)

    A conceptual design of fusion-fission hybrid reactor (FFHR) has been studied for transmutation. The FFHR is magnetic confinement fusion reactor with a blanket containing minor actinides (MAs) from nuclear waste reprocessed from three years cooled spent PWR fuels of 33 GWD/t with initial uranium enrichment of 3.3%. The same plasma conditions as ITER were referred for blanket design. The blanket system consists of MA pebbles coated with Ti nitride, cooling water, structure (F82H) and tritium breeding materials (Li2TiO3). A criticality (keff), Tritium Breeding Ratio (TBR) and energy multiplication (Q value) in the blanket were investigated by the Monte Carlo N-particle transport code MCNP-4C with the nuclear data library JENDL 3.3 after understanding heat calculations. The Q value of 105, fission power 1200 MWt and TBR of 1.8 were obtained at the both conditions of keff value of 0.95 and permissible temperatures in MA, F82H structure, Li2TiO3 and coolant. (author)

  5. UNEDF: Advanced Scientific Computing Transforms the Low-Energy Nuclear Many-Body Problem

    CERN Document Server

    Stoitsov, M; Nazarewicz, W; Bulgac, A; Hagen, G; Kortelainen, M; Pei, J C; Roche, K J; Schunck, N; Thompson, I; Vary, J P; Wild, S M

    2011-01-01

    The UNEDF SciDAC collaboration of nuclear theorists, applied mathematicians, and computer scientists is developing a comprehensive description of nuclei and their reactions that delivers maximum predictive power with quantified uncertainties. This paper illustrates significant milestones accomplished by UNEDF through integration of the theoretical approaches, advanced numerical algorithms, and leadership class computational resources.

  6. Incentives to strengthen international co-operation in R and D for advanced nuclear power technology

    International Nuclear Information System (INIS)

    This paper is concerned with the need for International Co-operation in R and D for Advanced Reactors in order to maintain options for the future deployment of nuclear power against the current background of declining R and D capability in Europe

  7. System study of CANDU/LWR synergy in advanced nuclear fuel cycles

    International Nuclear Information System (INIS)

    This report proposes a study that will evaluate the effects of advanced nuclear fuel cycles on resource utilisation, repository capacity, waste streams, economics, and proliferation resistance. The proposed fuel cycles are designed to exploit the unique synergy that exists between light water and CANDU reactors. Also, several fuel cycle simulation codes have been proposed to be used. (author)

  8. Nuclear β-catenin expression as a prognostic factor in advanced colorectal carcinoma

    Institute of Scientific and Technical Information of China (English)

    Adam Elzagheid; Abdelbaset Buhmeida; Eija Korkeila; Yrj(o) Collan; Karl Syrj(a)nen; Seppo Pyrh(o)nen

    2008-01-01

    AIM: To investigate the changing pattern of β-catenin expression and its prognostic value in advanced colorectal cancer (CRC).METHODS.Archival tumor samples were analyzed for β-catenin using immunohistochemisry (IHC) in 95 patients with advanced CRC.RESULTS: Membranous β-catenin expression was found in the normal colorectal epithelium.Almost 100% of CRCcases showed membranous and cytoplasmic expression,and 55 (58%) cases showed nuclear expression.In univariate (Kaplan-Meier)survival analysis,only the nuclear index (NI) was a significant predictor of disease free survival (DFS) (P=0.023; n = 35),with a NI above the median associated with longer DFS (34.2 mo) than those with a NI below the median (15.5 mo) (P = 0.045,ANOVA).The other indices were not significant predictors of DFS,and none of the three tested indices (for membranous,cytoplasmic,or nuclear expression) predicted diseasespecific survival (DSS).However,when dichotomized as positive or negative nuclear expression,the former was a significant predictor of more favorable DFS (P =0.041) and DSS (P = 0.046).CONCLUSION: Nuclear β-catenin expression provides additional information in predicting patient outcome in advanced CRC.

  9. Material performance evaluation -Development of the advanced nuclear materials-

    International Nuclear Information System (INIS)

    A multifrequency ACPD system was assembled. A SSRT equipment for stress corrosion cracking test was installed. A 25-ton capacity fatigue test machine was purchased as a first step to assemble a corrosion fatigue test facility. A test loop was designed to simulate the primary water chemistry condition. An Ag/AgCl external reference electrode which can be used at a temperature as high as 280 deg C was fabricated. A high temperature pH electrode was designed for fabrication. A creep test machine was designed conceptually for testing creep behaviors of Zr alloys. Preliminary design requirements were made for the instrumented capsule and a plan was made for using the uninstrumented capsule, as parts of activities to complete an integrated plan of in-reactor materials irradiation test. CHEC computer code which helped improving maintenance program against erosion/corrosion of secondary pipings of nuclear power plants was purchased. Erosion/corrosion of feedwater heater drain line of Kori Unit One was analyzed using the CHEC code as a sample calculation. (Author)

  10. Prescriptive concepts for advanced nuclear materials control and accountability systems

    International Nuclear Information System (INIS)

    Networking- and distributed-processing hardware and software have the potential of greatly enhancing nuclear materials control and accountability (MC and A) systems, from both safeguards and process operations perspectives, while allowing timely integrated safeguards activities and enhanced computer security at reasonable cost. A hierarchical distributed system is proposed consisting of groups of terminal and instruments in plant production and support areas connected to microprocessors that are connected to either larger microprocessors or minicomputers. These micros and/or minis are connected to a main machine, which might be either a mainframe or a super minicomputer. Data acquisition, preliminary input data validation, and transaction processing occur at the lowest level. Transaction buffering, resource sharing, and selected data processing occur at the intermediate level. The host computer maintains overall control of the data base and provides routine safeguards and security reporting and special safeguards analyses. The research described outlines the distribution of MC and A system requirements in the hierarchical system and distributed processing applied to MC and A. Implications of integrated safeguards and computer security concepts for the distributed system design are discussed. 10 refs., 4 figs

  11. Advanced Nuclear Power Concepts for Human Exploration Missions

    International Nuclear Information System (INIS)

    The design reference mission for the National Aeronautics and Space Administration's (NASA's) human mission to Mars supports a philosophy of living off the land in order to reduce crew risk, launch mass, and life-cycle costs associated with logistics resupply to a Mars base. Life-support materials, oxygen, water, and buffer gases, and the crew's ascent-stage propellant would not be brought from Earth but rather manufactured from the Mars atmosphere. The propellants would be made over ∼2 yr, the time between Mars mission launch window opportunities. The production of propellants is very power intensive and depends on type, amount, and time to produce the propellants. Closed-loop life support and food production are also power intensive. With the base having several habitats, a greenhouse, and propellant production capability, total power levels reach well over 125 kW(electric). The most mass-efficient means of satisfying these requirements is through the use of nuclear power. Studies have been performed to identify a potential system concept, described in this paper, using a mobile cart to transport the power system away from the Mars lander and provide adequate separation between the reactor and crew. The studies included an assessment of reactor and power conversion technology options, selection of system and component redundancy, determination of optimum separation distance, and system performance sensitivity to some key operating parameters

  12. Nuclear developments: the DMAX advanced reactor control system

    International Nuclear Information System (INIS)

    Framatome has recently developed a new system for controlling the rod cluster control assemblies of pressurized water reactors, called the DMAX. The associated reactor control method is called 'mode X'. The DMAX system will be installed in all 'N4' model Framatome nuclear steam supply systems, the first two of which are presently under construction on the Chooz site in France. It will enable fine controlling of the reactor coolant temperature and the axial power offset, entirely automatically, due to double closed-loop regulation. The new DMAX system allows temperature control and continuous maintenance of a stable reactor core power distribution, because of an original method for controlling the movements of the control rods within the reactor. The disturbing xenon oscillations are practically eliminated and the operator is freed from the need of constantly monitoring the axial power offset, which is necessary in the commonly used 'A' or 'G' control modes. The probability of penalizing initial conditions in case an incident or accident occurs is considerably reduced in mode X, with the DMAX system, and the reactor's load-following performances are improved. In addition, the reactivity variations that must necessarily be compensated for in mode G by changing the boric acid concentration of the reactor coolant can be simply compensated for by control rod movements in mode X. This possibility yields a major reduction in the volume of liquid effluents that must subsequently be created. The system is outlined and its operation explained. (author)

  13. Advanced filters for nuclear facilities and filter conditioning for disposal

    International Nuclear Information System (INIS)

    This paper reports the advantages of the cylinder shape selected for the filter elements for aerosol and iodine removal from the offgas of nuclear facilities, above all in view of remote and manual operation and transport, conditioning and disposal. In order to test the conditioning of polygonal HEPA filter elements, several filter elements not exposed to radioactivity were crushed remotely and embedded in concrete in a 400 l waste drum. The waste drum was subsequently saw cut in order to verify the quality of concrete embedding. The result of concrete embedding is satisfactory. The design is presented of a filter element capable of accommodating gas flows up to 500 m3/h for wet aerosol removal with a high removal efficiency. Also the design of a filter element for gas flows up to 800 m3/h to be used in iodine removal from offgases with low iodine contents is described. In order to be able to use the cylindrical filter elements developed for remote handling in manual operation too, e.g., for cleaning low level offgases, a manually operated filter housing was developed. It is suited for working pressures up to 10 bar and working temperatures up to 160 degree C. The filter elements are replaced by the usual bagging technique

  14. Advanced handbook for accident analyses of German nuclear power plants

    International Nuclear Information System (INIS)

    The advanced handbook of safety analyses (HSA) comprises a comprehensive electronic collection of knowledge for the compilation and conduction of safety analyses in the area of reactor, plant and containment behaviour as well as results of existing safety analyses (performed by GRS in the past) with characteristic specifications and further background information. In addition, know-how from the analysis software development and validation process is presented and relevant rules and regulations with regard to safety demonstration are provided. The HSA comprehensively covers the topic thermo-hydraulic safety analyses (except natural hazards, man-made hazards and malicious acts) for German pressurized and boiling water reactors for power and non-power operational states. In principle, the structure of the HSA-content represents the analytical approach utilized by safety analyses and applying the knowledge from safety analyses to technical support services. On the basis of a multilevel preparation of information to the topics ''compilation of safety analyses'', ''compilation of data bases'', ''assessment of safety analyses'', ''performed safety analyses'', ''rules and regulation'' and ''ATHLET-validation'' the HSA addresses users with different background, allowing them to enter the HSA at different levels. Moreover, the HSA serves as a reference book, which is designed future-oriented, freely configurable related to the content, completely integrated into the GRS internal portal and prepared to be used by a growing user group.

  15. Advanced methods of quality control in nuclear fuel fabrication

    International Nuclear Information System (INIS)

    Under pressure of current economic and electricity market situation utilities implement more demanding fuel utilization schemes including higher burn ups and thermal rates, longer fuel cycles and usage of Mo fuel. Therefore, fuel vendors have recently initiated new R and D programmes aimed at improving fuel quality, design and materials to produce robust and reliable fuel. In the beginning of commercial fuel fabrication, emphasis was given to advancements in Quality Control/Quality Assurance related mainly to product itself. During recent years, emphasis was transferred to improvements in process control and to implementation of overall Total Quality Management (TQM) programmes. In the area of fuel quality control, statistical control methods are now widely implemented replacing 100% inspection. This evolution, some practical examples and IAEA activities are described in the paper. The paper presents major findings of the latest IAEA Technical Meetings (TMs) and training courses in the area with emphasis on information received at the TM and training course held in 1999 and other latest publications to provide an overview of new developments in process/quality control, their implementation and results obtained including new approaches to QC

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

    International Nuclear Information System (INIS)

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

  17. Study of potential of nuclear waste transmutation and safety characteristics of an hybrid system: sub critical accelerator reactor

    International Nuclear Information System (INIS)

    The study of potential of nuclear waste transmutation for the new reactor systems - hybrid reactors - was the object of this work. Global review of different projects is presented. The basic physical parameters definitions, as neutron surplus and relative importance of external source neutrons, are introduced and explained. For these parameters, numerical values are obtained. The advantage in neutron surplus of fast system is noted. Equilibrium model and corresponding toxicities of different isotopes nd nuclear cycles are presented. Numerical analysis for equilibrium model converge validation are performed also. The study of neutron consumption by 'transmutable' Long-Lived Fission Products (Tc, I and Cs) show the possibility of their incineration in dedicated fast hybrid reactors. Equilibrium model shown the influence of reprocessing losses level to cycle toxicity level. Relations between specific fuel inventories (mass normalised by power unit) for thermal and fast spectra are examined. The differences are relatively small. Finally, few hybrid reactor concepts with different objects were analysed. These studies confirm that in frameworks of certain Nuclear Energy scenarios the fast hybrid systems can reduce significantly the radio-toxicity of fuel cycle. Preliminary analyses of sub-critical reactor behaviour show big potential of this reactor type in 'Transient of Power' kind of accident, even if more detailed study is necessary. (author)

  18. Response of inbred and hybrid maize seed to gamma radiation and fission neutrons and its relationship to nuclear volume

    International Nuclear Information System (INIS)

    Measurements have been made of dose-response curves and relative biological effectiveness (RBE) for seedling growth reduction following seed irradiation of four inbreds, three single-cross hybrids, and one double-cross hybrid of maize with γ-radiation and fission neutrons. Also of primary interest was the relationship of response differences to nuclear volume. Caryopses (seeds) were adjusted to a water content of 13 to 14% prior to irradiation. Nuclear volumes were determined from nuclei in cells of the apical meristem. The inbred T232 was approximately 3 and 1.5 to 2 times more sensitive to γ-radiation and fission neutrons, respectively, than the other inbreds and hybrids. Except for T232, the D50 for γ-radiation was 35 to 40 krads. The response to fission neutrons was more variable; D50 s ranged from 0.79 krads for T232 to 1.79 krads for the double cross hybrid. This resulted in differences in neutron RBE, which ranged from 17.5 for T232 to 35.6 for the inbred T220. There was no consistent relationship between response to either kind of radiation and nuclear volume. (author)

  19. Proceedings of the fourth international symposium on advanced nuclear energy research

    International Nuclear Information System (INIS)

    The papers presented and discussed in the 4th International Symposium on Advanced Nuclear Energy Research, of which subject was focussed on the Roles and Direction of Material Science in Nuclear Technology are contained. The sessions organized for the aural session of the symposium were (1) Processing Science for New Materials, (2) New Tools for Advanced Materials Research, (3) Challenge of Materials Database and (4) Frontier of Materials Technology in New Power Systems, from which 18 invited and 77 contributed papers were selected for the publication. The volume includes also summaries of the panel discussions titled as (1) Computer Simulation for Materials Innovation and (2) What is Expected for Materials Science in Future Nuclear Energy Developments ?, with which a complete recording of the discussions for the latter subject was attempted by the Editorial Working Group of the Program Committee. The 65 of the presented papers are indexed individually. (J.P.N.)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  2. State-of-the-art Report on Innovative Fuels for Advanced Nuclear Systems

    International Nuclear Information System (INIS)

    Development of innovative fuels such as homogeneous and heterogeneous fuels, ADS fuels, and oxide, metal, nitride and carbide fuels is an important stage in the implementation process of advanced nuclear systems. Several national and international R and D programmes are investigating minor actinide-bearing fuels due to their ability to help reduce the radiotoxicity of spent fuel and therefore decrease the burden on geological repositories. Minor actinides can be converted into a suitable fuel form for irradiation in reactor systems where they are transmuted into fission products with a significantly shorter half-life. This report compares recent studies of fuels containing minor actinides for use in advanced nuclear systems. The studies review different fuels for several types of advanced reactors by examining various technical issues associated with fabrication, characterisation, irradiation performance, design and safety criteria, as well as technical maturity. (authors)

  3. Recent Advances in Development of Herbicide Resistant Transgenic Hybrid Rice in China

    Institute of Scientific and Technical Information of China (English)

    XIAO Guo-ying

    2009-01-01

    In addition to weed control in direct seeding field of hybrid rice, herbicide resistance genes were used by Chinese scientists to increase and identify the purity of hybrid seeds, and to realize the mechanization of hybrid seed production. The elite restorer lines, such as Minghui 63, R752, T461, R402, D68 and E32 were transformed directly with herbicide resistance genes, in which D68 and E32 are restorer lines of two-line system and the others are of three-line system. Because almost all of important restorer lines are indica varieties and are recalcitrant in transformation, many herbicide resistant near-isogenic restorer lines were developed by sexual hybridization of indica and japonica varieties and backcross with indica restorer lines later, such as Ce 64, Minghui 63, Teqing, Milyang 46, R402 and 9311, in which 9311 is a restorer line of two-line system. The elite photoperiod-sensitive/thermo-sensitive genic male sterile lines, such as Pei'ai 64S, P88S, 4008S and 7001S, were transformed with herbicide resistance genes. A few herbicide resistant male sterile lines were developed through sexual hybridization and subsequently systemic selection, such as Bar1259S, Bar2172S, 05Z221A and 05Z227A. With the employment of herbicide resistant male sterile lines or herbicide resistant restorer lines, a few herbicide resistant hybrid rice combinations were developed, such as Xiang 125S/Bar 68-1 and Pei'ai 64S/Bar 9311. Based on herbicide resistance, the research was marching on to investigate the parental lines of hybrid rice with insect resistance, drought tolerance, etc.

  4. A Crewed Mission to Apophis Using a Hybrid Bimodal Nuclear Thermal Electric Propulsion (BNTEP) System

    Science.gov (United States)

    Mccurdy, David R.; Borowski, Stanley K.; Burke, Laura M.; Packard, Thomas W.

    2014-01-01

    A BNTEP system is a dual propellant, hybrid propulsion concept that utilizes Bimodal Nuclear Thermal Rocket (BNTR) propulsion during high thrust operations, providing 10's of kilo-Newtons of thrust per engine at a high specific impulse (Isp) of 900 s, and an Electric Propulsion (EP) system during low thrust operations at even higher Isp of around 3000 s. Electrical power for the EP system is provided by the BNTR engines in combination with a Brayton Power Conversion (BPC) closed loop system, which can provide electrical power on the order of 100's of kWe. High thrust BNTR operation uses liquid hydrogen (LH2) as reactor coolant propellant expelled out a nozzle, while low thrust EP uses high pressure xenon expelled by an electric grid. By utilizing an optimized combination of low and high thrust propulsion, significant mass savings over a conventional NTR vehicle can be realized. Low thrust mission events, such as midcourse corrections (MCC), tank settling burns, some reaction control system (RCS) burns, and even a small portion at the end of the departure burn can be performed with EP. Crewed and robotic deep space missions to a near Earth asteroid (NEA) are best suited for this hybrid propulsion approach. For these mission scenarios, the Earth return V is typically small enough that EP alone is sufficient. A crewed mission to the NEA Apophis in the year 2028 with an expendable BNTEP transfer vehicle is presented. Assembly operations, launch element masses, and other key characteristics of the vehicle are described. A comparison with a conventional NTR vehicle performing the same mission is also provided. Finally, reusability of the BNTEP transfer vehicle is explored.

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

    International Nuclear Information System (INIS)

    In this year (the second year of this project), researches and development have been carried out to establish the essential key technologies applied to robot system for nuclear industry. In the area of robot vision, in order to construct stereo vision system necessary to tele-operation, stereo image acquisition camera module and stereo image displayer have been developed. Stereo matching and storing programs have been developed to analyse stereo images. According to the result of tele-operation experiment, operation efficiency has been enhanced about 20% by using the stereo vision system. In a part of object recognition, a tele-operated robot system has been constructed to evaluate the performance of the stereo vision system and to develop the vision algorithm to automate nozzle dam operation. A nuclear fuel rod character recognition system has been developed by using neural network. As a result of perfomance evaluation of the recognition system, 99% recognition rate has been achieved. In the area of sensing and intelligent control, temperature distribution has been measured by using the analysis of thermal image histogram and the inspection algorithm has been developed to determine of the state be normal or abnormal, and the fuzzy controller has been developed to control the compact mobile robot designed for path moving on block-typed path. (Author)

  6. An advanced NSSS integrity monitoring system for Shin-Kori nuclear units 3 and 4

    International Nuclear Information System (INIS)

    The advanced design features of NSSS (Nuclear Steam Supply System) Integrity Monitoring System for Shin-Kori Nuclear Units 3 and 4 are summarized herein. During the overall system design and detailed component design processes, many design improvements have been made for the system. The major design changes are: 1) the application of a common software platform for all subsystems, 2) the implementation of remote access, control and monitoring capabilities, and 3) the equipment redesign and rearrangement that has simplified the system architecture. Changes give an effect on cabinet size, number of cables, cyber-security, graphic user interfaces, and interfaces with other monitoring systems. The system installation and operation for Shin-Kori Nuclear Units 3 and 4 will be more convenient than those for previous Korean nuclear units in view of its remote control capability, automated test functions, improved user interface functions, and much less cabling. (authors)

  7. Bulk-Flow Analysis of Hybrid Thrust Bearings for Advanced Cryogenic Turbopumps

    Science.gov (United States)

    SanAndres, Luis

    1998-01-01

    on a Windows 95/NT personal computer. The program, help files and examples are licensed by Texas A&M University Technology License Office. The study of the static and dynamic performance of two hydrostatic/hydrodynamic bearings demonstrates the importance of centrifugal and advection fluid inertia effects for operation at high rotational speeds. The first example considers a conceptual hydrostatic thrust bearing for an advanced liquid hydrogen turbopump operating at 170,000 rpm. The large axial stiffness and damping coefficients of the bearing should provide accurate control and axial positioning of the turbopump and also allow for unshrouded impellers, therefore increasing the overall pump efficiency. The second bearing uses a refrigerant R134a, and its application in oil-free air conditioning compressors is of great technological importance and commercial value. The computed predictions reveal that the LH2 bearing load capacity and flow rate increase with the recess pressure (i.e. increasing orifice diameters). The bearing axial stiffness has a maximum for a recess pressure rati of approx. 0.55. while the axial damping coefficient decreases as the recess pressure ratio increases. The computer results from three flow models are compared. These models are a) inertialess, b) fluid inertia at recess edges only, and c) full fluid inertia at both recess edges and film lands. The full inertia model shows the lowest flow rates, axial load capacity and stiffness coefficient but on the other hand renders the largest damping coefficients and inertia coefficients. The most important findings are related to the reduction of the outflow through the inner radius and the appearance of subambient pressures. The performance of the refrigerant hybrid thrust bearing is evaluated at two operating speeds and pressure drops. The computed results are presented in dimensionless form to evidence consistent trends in the bearing performance characteristics. As the applied axial load

  8. A hybrid approach to solving the problem of design of nuclear fuel cells; Un enfoque hibrido para la solucion del problema del diseno de celdas de combustible nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Montes T, J. L.; Perusquia del C, R.; Ortiz S, J. J.; Castillo, A., E-mail: joseluis.montes@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2015-09-15

    An approach to solving the problem of fuel cell design for BWR power reactor is presented. For this purpose the hybridization of a method based in heuristic knowledge rules called S15 and the advantages of a meta-heuristic method is proposed. The synergy of potentialities of both techniques allows finding solutions of more quality. The quality of each solution is obtained through a multi-objective function formed from the main cell parameters that are provided or obtained during the simulation with the CASMO-4 code. To evaluate this alternative of solution nuclear fuel cells of reference of nuclear power plant of Laguna Verde were used. The results show that in a systematic way the results improve when both methods are coupled. As a result of the hybridization process of the mentioned techniques an improvement is achieved in a range of 2% with regard to the achieved results in an independent way by the S15 method. (Author)

  9. Efficiency and cost advantages of an advanced-technology nuclear electrolytic hydrogen-energy production facility

    Science.gov (United States)

    Donakowski, T. D.; Escher, W. J. D.; Gregory, D. P.

    1977-01-01

    The concept of an advanced-technology (viz., 1985 technology) nuclear-electrolytic water electrolysis facility was assessed for hydrogen production cost and efficiency expectations. The facility integrates (1) a high-temperature gas-cooled nuclear reactor (HTGR) operating a binary work cycle, (2) direct-current (d-c) electricity generation via acyclic generators, and (3) high-current-density, high-pressure electrolyzers using a solid polymer electrolyte (SPE). All subsystems are close-coupled and optimally interfaced for hydrogen production alone (i.e., without separate production of electrical power). Pipeline-pressure hydrogen and oxygen are produced at 6900 kPa (1000 psi). We found that this advanced facility would produce hydrogen at costs that were approximately half those associated with contemporary-technology nuclear electrolysis: $5.36 versus $10.86/million Btu, respectively. The nuclear-heat-to-hydrogen-energy conversion efficiency for the advanced system was estimated as 43%, versus 25% for the contemporary system.

  10. Nuclear Hybrid Energy System: Molten Salt Energy Storage (Summer Report 2013)

    Energy Technology Data Exchange (ETDEWEB)

    Piyush Sabharwall; Michael George mckellar; Su-Jong Yoon

    2013-11-01

    Effective energy use is a main focus and concern in the world today because of the growing demand for energy. The nuclear hybrid energy system (NHES) is a valuable technical concept that can potentially diversify and leverage existing energy technologies. This report considers a particular NHES design that combines multiple energy systems including a nuclear reactor, energy storage system (ESS), variable renewable generator (VRG), and additional process heat applications. Energy storage is an essential component of this particular NHES because its design allows the system to produce peak power while the nuclear reactor operates at constant power output. Many energy storage options are available, but this study mainly focuses on a molten salt ESS. The primary purpose of the molten salt ESS is to enable the nuclear reactor to be a purely constant heat source by acting as a heat storage component for the reactor during times of low demand, and providing additional capacity for thermo-electric power generation during times of peak electricity demand. This report will describe the rationale behind using a molten salt ESS and identify an efficient molten salt ESS configuration that may be used in load following power applications. Several criteria are considered for effective energy storage and are used to identify the most effective ESS within the NHES. Different types of energy storage are briefly described with their advantages and disadvantages. The general analysis to determine the most efficient molten salt ESS involves two parts: thermodynamic, in which energetic and exergetic efficiencies are considered; and economic. Within the molten salt ESS, the two-part analysis covers three major system elements: molten salt ESS designs (two tank direct and thermocline), the molten salt choice, and the different power cycles coupled with the molten salt ESS. Analysis models are formulated and analyzed to determine the most effective ESS. The results show that the most

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

    International Nuclear Information System (INIS)

    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. It has been looking for these techniques to expand the working area of human, raise the working efficiencies of remote task to the highest degree, and enhance the industrial

  12. 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).

  13. Advances in Nuclear Forensics: Countering the Evolving Threat of Nuclear and Other Radioactive Material out of Regulatory Control. Summary of an International Conference

    International Nuclear Information System (INIS)

    The International Conference on Advances in Nuclear Forensics: Countering the Evolving Threat of Nuclear and Other Radioactive Material out of Regulatory Control was organized by the IAEA and held in Vienna on 7–10 July 2014. The conference was organized in cooperation with the Nuclear Forensics International Technical Working Group (ITWG), the International Criminal Police Organization (INTERPOL) and the Global Initiative to Combat Nuclear Terrorism (GICNT). The conference was attended by 285 participants and observers from 76 Member States and 8 organizations. The objective of the conference was: to convene the first of its kind international conference solely dedicated to nuclear forensics: to review the role of nuclear forensics as an essential element of a nuclear security infrastructure; to present scientific achievements and to exchange experience and lessons learned on the implementation of nuclear forensics in support of law enforcement investigations and nuclear security vulnerability assessments; to review current practices in nuclear forensics and to identify advances in analytical tools; to discuss ways of strengthening nuclear forensic capabilities and capacity building in nuclear forensics to ensure sustainability; and to explore mechanisms to enhance international and regional cooperation in nuclear forensics as well as to best position the IAEA to provide assistance to States, upon request, in nuclear forensics. This publication provides the President’s summary and findings of the conference as well as summaries of all the sessions. The accompanying CD-ROM contains the full conference programme, the list of participants and the papers

  14. Strategic Plan for Nuclear Energy -- Knowledge Base for Advanced Modeling and Simulation (NE-KAMS)

    Energy Technology Data Exchange (ETDEWEB)

    Kimberlyn C. Mousseau

    2011-10-01

    The Nuclear Energy Computational Fluid Dynamics Advanced Modeling and Simulation (NE-CAMS) system is being developed at the Idaho National Laboratory (INL) in collaboration with Bettis Laboratory, Sandia National Laboratory (SNL), Argonne National Laboratory (ANL), Utah State University (USU), and other interested parties with the objective of developing and implementing a comprehensive and readily accessible data and information management system for computational fluid dynamics (CFD) verification and validation (V&V) in support of nuclear energy systems design and safety analysis. The two key objectives of the NE-CAMS effort are to identify, collect, assess, store and maintain high resolution and high quality experimental data and related expert knowledge (metadata) for use in CFD V&V assessments specific to the nuclear energy field and to establish a working relationship with the U.S. Nuclear Regulatory Commission (NRC) to develop a CFD V&V database, including benchmark cases, that addresses and supports the associated NRC regulations and policies on the use of CFD analysis. In particular, the NE-CAMS system will support the Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program, which aims to develop and deploy advanced modeling and simulation methods and computational tools for reliable numerical simulation of nuclear reactor systems for design and safety analysis. Primary NE-CAMS Elements There are four primary elements of the NE-CAMS knowledge base designed to support computer modeling and simulation in the nuclear energy arena as listed below. Element 1. The database will contain experimental data that can be used for CFD validation that is relevant to nuclear reactor and plant processes, particularly those important to the nuclear industry and the NRC. Element 2. Qualification standards for data evaluation and classification will be incorporated and applied such that validation data sets will result in well

  15. Assessment of fiber optic sensors and other advanced sensing technologies for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hashemian, H.M. [Analysis and Measurement Services Corporation, Knoxville, TN (United States)

    1996-03-01

    As a result of problems such as calibration drift in nuclear plant pressure sensors and the recent oil loss syndrome in some models of Rosemount pressure transmitters, the nuclear industry has become interested in fiber optic pressure sensors. Fiber optic sensing technologies have been considered for the development of advanced instrumentation and control (I&C) systems for the next generation of reactors and in older plants which are retrofitted with new I&C systems. This paper presents the results of a six-month Phase I study to establish the state-of-the-art in fiber optic pressure sensing. This study involved a literature review, contact with experts in the field, an industrial survey, a site visit to a fiber optic sensor manufacturer, and laboratory testing of a fiber optic pressure sensor. The laboratory work involved both static and dynamic performance tests. This initial Phase I study has recently been granted a two-year extension by the U.S. Nuclear Regulatory Commission (NRC). The next phase will evaluate fiber optic pressure sensors in specific nuclear plant applications in addition to other advanced methods for monitoring critical nuclear plant equipment.

  16. 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.

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

    International Nuclear Information System (INIS)

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

  18. Utility leadership in reopening the nuclear option with advanced light water reactors

    Energy Technology Data Exchange (ETDEWEB)

    Marston, T.U.; Layman, W.H. (Electric Power Research Institute, Palo Alto, CA (United States))

    1992-01-01

    Since 1981, the Electric Power Research Institute (EPRI) has been pursing the development of the advanced light water reactor (ALWR). The ALWR Program is comprised of five phases and are described in the paper. In order to meet the anticipated baseline power generation requirements in the US, the Nuclear Power Oversight Committee (NPOC) has developed a strategic plan for ALWR implementation in order to regain the nuclear option in the United States. The paper also covers the policies behind the utility requirements, the status of ALWR developments in the United States, the electricity demands during the period 1990-2010, and some of the innovative features of the passive plants presently under design.

  19. Axial enrichment profile in advance nuclear energy power plant at supercritical-pressures

    Energy Technology Data Exchange (ETDEWEB)

    Tashakor, S. [Nuclear Science and Technology Research Institute (NSTRI), Tehran (Iran, Islamic Republic of). Reactor Research School; Islamic Azad Univ., Shiraz (Iran, Islamic Republic of). Dept. of Nuclear Engineering; Zarifi, E. [Nuclear Science and Technology Research Institute (NSTRI), Tehran (Iran, Islamic Republic of). Reactor Research School; Salehi, A.A. [Sharif University of Technology, Tehran (Iran, Islamic Republic of). Dept. of Nuclear Energy

    2015-12-15

    The High-Performance Light Water Reactor (HPLWR) is the European version of the advance nuclear energy power plant at Supercritical-pressure. A light water reactor at supercritical pressure, being currently under design, is the new generation of nuclear reactors. The aim of this study is to predict the HPLWR neutronic behavior of the axial enrichment profile with an average enrichment of 5 w/o U-235. Neutronic calculations are performed using WIMS and CITATION codes. Changes in neutronic parameter, such as Power Peaking Factor (PPF) are discussed in this paper.

  20. Utility leadership in reopening the nuclear option with advanced light water reactors

    International Nuclear Information System (INIS)

    Since 1981, the Electric Power Research Institute (EPRI) has been pursing the development of the advanced light water reactor (ALWR). The ALWR Program is comprised of five phases and are described in the paper. In order to meet the anticipated baseline power generation requirements in the US, the Nuclear Power Oversight Committee (NPOC) has developed a strategic plan for ALWR implementation in order to regain the nuclear option in the United States. The paper also covers the policies behind the utility requirements, the status of ALWR developments in the United States, the electricity demands during the period 1990-2010, and some of the innovative features of the passive plants presently under design

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

    International Nuclear Information System (INIS)

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

  2. Recent advances of annular centrifugal extractor for hot test of nuclear waste partitioning process

    Institute of Scientific and Technical Information of China (English)

    HeXiang-Ming; YanYu-Shun; 等

    1998-01-01

    Advances are being made in the design of the annular centrifugal extractor fornuclear fuel reprocessing extraction process studies.The extractors have been built and tested.Twelve stages of this extractor and 50 stages are used toimplement the TRPO process for the cleanup ofcommercial and defense nuclear waste liquids,respectively.Following advances are available:(1) simple way of assembly and disassembly between rotor part and housing part of extractor,ease of manipulator operation;(2)automatic sampling from housing of extractor in hot cell;(3) compact multi-stage housing system;(4) easy interstage link;(5) computer data acquisition and monitoring system of speed.

  3. Recent Advances in Computational Methods for Nuclear Magnetic Resonance Data Processing

    KAUST Repository

    Gao, Xin

    2013-01-11

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

  4. Hybrid systems for transuranic waste transmutation in nuclear power reactors: state of the art and future prospects

    International Nuclear Information System (INIS)

    The features of subcritical hybrid systems (HSs) are discussed in the context of burning up transuranic wastes from the U-Pu nuclear fuel cycle. The advantages of HSs over conventional atomic reactors are considered, and fuel cycle closure alternatives using HSs and fast neutron reactors are comparatively evaluated. The advantages and disadvantages of two HS types with neutron sources (NSs) of widely different natures -- nuclear spallation in a heavy target by protons and nuclear fusion in magnetically confined plasma -- are discussed in detail. The strengths and weaknesses of HSs are examined, and demand for them for closing the U-Pu nuclear fuel cycle is assessed. (instruments and methods of investigation)

  5. The Path to Sustainable Nuclear Energy. Basic and Applied Research Opportunities for Advanced Fuel Cycles

    Energy Technology Data Exchange (ETDEWEB)

    Finck, P.; Edelstein, N.; Allen, T.; Burns, C.; Chadwick, M.; Corradini, M.; Dixon, D.; Goff, M.; Laidler, J.; McCarthy, K.; Moyer, B.; Nash, K.; Navrotsky, A.; Oblozinsky, P.; Pasamehmetoglu, K.; Peterson, P.; Sackett, J.; Sickafus, K. E.; Tulenko, J.; Weber, W.; Morss, L.; Henry, G.

    2005-09-01

    The objective of this report is to identify new basic science that will be the foundation for advances in nuclear fuel-cycle technology in the near term, and for changing the nature of fuel cycles and of the nuclear energy industry in the long term. The goals are to enhance the development of nuclear energy, to maximize energy production in nuclear reactor parks, and to minimize radioactive wastes, other environmental impacts, and proliferation risks. The limitations of the once-through fuel cycle can be overcome by adopting a closed fuel cycle, in which the irradiated fuel is reprocessed and its components are separated into streams that are recycled into a reactor or disposed of in appropriate waste forms. The recycled fuel is irradiated in a reactor, where certain constituents are partially transmuted into heavier isotopes via neutron capture or into lighter isotopes via fission. Fast reactors are required to complete the transmutation of long-lived isotopes. Closed fuel cycles are encompassed by the Department of Energy?s Advanced Fuel Cycle Initiative (AFCI), to which basic scientific research can contribute. Two nuclear reactor system architectures can meet the AFCI objectives: a ?single-tier? system or a ?dual-tier? system. Both begin with light water reactors and incorporate fast reactors. The ?dual-tier? systems transmute some plutonium and neptunium in light water reactors and all remaining transuranic elements (TRUs) in a closed-cycle fast reactor. Basic science initiatives are needed in two broad areas: ? Near-term impacts that can enhance the development of either ?single-tier? or ?dual-tier? AFCI systems, primarily within the next 20 years, through basic research. Examples: Dissolution of spent fuel, separations of elements for TRU recycling and transmutation Design, synthesis, and testing of inert matrix nuclear fuels and non-oxide fuels Invention and development of accurate on-line monitoring systems for chemical and nuclear species in the nuclear

  6. Advanced control systems to improve nuclear power plant reliability and efficiency

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2005-07-01

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

  8. Strategy for nuclear wastes incineration in hybrid reactors; Strategies pour l'incineration de dechets nucleaires dans des reacteurs hybrides

    Energy Technology Data Exchange (ETDEWEB)

    Lelievre, F

    1998-12-11

    The transmutation of nuclear wastes in accelerator-driven nuclear reactorsoffers undeniable advantages. But before going into the detailed study of a particular project, we should (i) examine the possible applications of such systems and (ii) compare the different configurations, in order to guide technological decisions. We propose an approach, answering both concerns, based on the complete description of hybrid reactors. It is possible, with only the transmutation objective and a few technological constraints chosen a posteriori, to determine precisely the essential parameters of such reactors: number of reactors, beam current, size of the core, sub-criticality... The approach also clearly pinpoints the strategic decisions, for which the scientist or engineer is not competent. This global scheme is applied to three distinct nuclear cycles: incineration of solid fuel without recycling, incineration of liquid fuel without recycling and incineration of liquid fuel with on-line recycling; and for two spectra, either thermal or fast. We show that the radiotoxicity reduction with a solid fuel is significant only with a fast spectrum, but the incineration times range from 20 to 30 years. The liquid fuel is appropriate only with on-line recycling, at equilibrium. The gain on the radiotoxicity can be considerable and we describe a number of such systems. The potential of ADS for the transmutation of nuclear wastes is confirmed, but we should continue the description of specific systems obtained through this approach. (author)

  9. Impact of high energy heavy ion nuclear collisions on advancement of nuclear physics

    International Nuclear Information System (INIS)

    The contributions of low energy heavy ion research to the inventions in nuclear physics are highlighted. The theoretical ideas used in their interpretations are qualitatively discussed. The survey of the literature relevant to charged particle spectroscopy and reactions with heavy ions is presented. The light projectile collision work and its relevant physics is also briefly summarized. In light of this, few suggestions are made to effectively use our heavy ion facilities. (author). 4 refs

  10. Advanced simulation strategies of dynamic regimes in nuclear plants in order to increase the nuclear safety

    International Nuclear Information System (INIS)

    Since the design period of Cernavoda NPP, Unit 2, performing thermal hydraulic analysis for nuclear power plants of Romania has become a priority for Romanian research and design institutes. As a result a number of 26 thermal-hydraulic analyses was achieved to support systems responsible for nuclear safety. This constituted a first step in investigating the complex field of thermo-hydraulic analysis. In this paper I will briefly present some of the results obtained and the proposed changes to Unit 2 at Cernavoda NPP in effecting the following analyses. The paper will present also some conclusions from the analysis on several systems from the secondary circuit, namely Feedwater System, Main Steam System and Main Condensate System. In these analyses we have been studied all the operating modes given by the system design manuals. The paper is limited to analysis of regimes involving changes in safety philosophy of the plant or plant operating procedures. By making these thermo-hydraulic analyses for Cernavoda NPP it was proven the Romanian design capability of making complete and consistent safety analyses for nuclear power plants as a first step towards independence from foreign support in implementing all necessary thermal-hydraulic analyses for future units that will be designed and made in Romania. (author)

  11. Enterprise SRS: Leveraging Ongoing Operations to Advance Nuclear Fuel Cycle Programs - 12579

    International Nuclear Information System (INIS)

    The international leadership in nuclear technology development and deployment long held by the United States has eroded due to the lack of clear national strategies for advanced reactor fuel cycle concepts and for nuclear materials management, as well as to the recent policy decision that halts work on the nuclear fuel repository at Yucca Mountain. Although no national consensus on strategy has yet been reached, a number of recent high-profile reviews and workshops have clearly highlighted a national need for robust research, development and deployment (RD and D) programs in key areas of nuclear technology, especially nuclear separations science and engineering. Collectively, these reviews and workshops provide a picture of the nuclear separations mission needs for three major program offices: Department of Energy Office of-Environmental Management), DOE Office of Nuclear Energy), and the National Nuclear Security Administration (NNSA). While the individual program needs differ significantly in detail and timing, they share common needs in two critical areas of RD and D: - The need for access to and use of multi-purpose engineering-scale demonstration test facilities that can support testing with radioactive material, and - The need for collaborative research enterprises that encompass government research organizations (i.e., national laboratories), commercial industry and the academic community. Such collaborative enterprises effectively integrate theory and modeling with the actual experimental work at all scales, as well as strengthen the technical foundation for research in critical areas. The arguments for engineering-scale collaborative research facilities are compelling. Processing history has shown that test programs and demonstrations conducted with actual nuclear materials are essential to program success. It is widely recognized, however, that such facilities are expensive to build and maintain; creating an imposing, if not prohibitive, financial burden

  12. Application of advanced statistical methods in assessment of the late phase of a nuclear accident

    Czech Academy of Sciences Publication Activity Database

    Hofman, Radek

    Praha: ČVUT, 2008, s. 1-4. [Dny radiacni ochrany /30/.. Liptovsky Jan (SK), 10.11.2008-14.11.2008] R&D Projects: GA ČR(CZ) GA102/07/1596 Institutional research plan: CEZ:AV0Z10750506 Keywords : radiation protection Subject RIV: DI - Air Pollution ; Quality http://library.utia.cas.cz/separaty/2008/AS/hofman-application of advanced statistical methods in assessment of the late phase of a nuclear accident.pdf

  13. Advanced Control Structures of Turbo Generator System of Nuclear Power Plant

    OpenAIRE

    Paweł Sokólski; Karol Kulkowski; Anna Kobylarz; Kazimierz Duzinkiewicz; Tomasz A. Rutkowski; Michał Grochowski

    2015-01-01

    In the paper a synthesis of advanced control structures of turbine and synchronous generator for nuclear power plant working under changing operating conditions (supplied power level) is presented. It is based on the nonlinear models of the steam turbine and synchronous generator cooperating with the power system. The considered control structure consists of multi-regional fuzzy control systems with local linear controllers, including PID controllers, in particular control loops of turbine...

  14. Fuel performance analysis of the Korea advanced nuclear fuel using ESCORE

    International Nuclear Information System (INIS)

    The Lead Use Assembly (LUA) of the Korea advanced nuclear fuel will be loaded in YGN4 cycle 7. The core cycle length is 16,248 MWD/MTU and 57,996 MWD/MTU is the maximum pin peak burnup. Fuel thermal and mechanical performance (i.e. maximum temperature, rod internal pressure, and cladding corrosion) evaluation is performed with ESCORE code which is developed by EPRI

  15. Nuclear fuel cycles of WWER-1000 at Kozloduy NPP: a program for transition to advanced fuel

    International Nuclear Information System (INIS)

    A systematical approach for WWER nuclear fuel utilization improvement is applied at the Kozloduy NPP while observing safety requirements. The fuel assemblies utilization for 4 years, higher burnup and reducing of high-activity radioactive waste will be achieved by realization of Activities program for transition of Units 5 and 6 of Kozloduy NPP to operating with Alternative Fuel Assemblies (AFA). The specified results from advanced fuel introduction also will improve the economic indices of Units 5 and 6 operation at Kozloduy NPP

  16. Human factors survey of advanced instrumentation and controls technologies in nuclear plants

    International Nuclear Information System (INIS)

    A survey of advanced instrumentation and controls (I ampersand C) technologies and associated human factors issues in the US and Canadian nuclear industries was carried out by a team from Oak Ridge national laboratory to provide background for the development of regulatory policy, criteria, and guides for review of advanced I ampersand C systems as well as human engineering guidelines for evaluating these systems. The survey found those components of the US nuclear industry surveyed to be quite interested in advanced I ampersand C, but very cautious in implementing such systems in nuclear facilities and power plants. The trend in the facilities surveyed is to experiment cautiously when there is an intuitive advantage or short-term payoff. In the control room, the usual practice is direct substitution of digital and microprocessor-based instruments or systems that are functionally identical to the analog instruments or systems being replaced. The most advanced I ampersand C systems were found in the Canadian CANDU plants, where the newest plant has digital system in almost 100% of its control systems and in over 70% of its plant protection system. The hypothesis that properly 'introducing digital systems increases safety' is supported by the Canadian experience. The performance of these digital systems was achieved using an appropriate quality assurance program for the software development. The ability of digital systems to detect impending failures and initiate a fail-safe action, is a significant safety issue that should be of special interest to every US utility as well as to the US Nuclear Regulatory Commission. (orig.)

  17. Human factors issues associated with advanced instrumentation and controls technologies in nuclear plants

    International Nuclear Information System (INIS)

    A survey of advanced instrumentation and controls (I ampersand C) technologies and associated human factors issues in the US and Canadian nuclear industries was carried out by a team from Oak Ridge national laboratory to provide background for the development of regulatory policy, criteria, and guides for review of advanced I ampersand C systems as well as human engineering guidelines for evaluating these systems. The survey found those components of the US nuclear industry surveyed to be quite interested in advanced I ampersand C, but very cautious in implementing such systems in nuclear facilities and power plants. The trend in the facilities surveyed is to experiment cautiously when there is an intuitive advantage or short-term payoff. In the control room, the usual practice is direct substitution of digital and microprocessor-based instruments or systems that are functionally identical to the analog instruments or systems being replaced. The most advanced I ampersand C systems were found in the Canadian CANDU plants, where the newest plant has digital system in almost 100% of its control systems and in over 70% of its plant protection system. The hypothesis that properly ''introducing digital systems increases safety'' is supported by the Canadian experience. The performance of these digital systems was achieved using an appropriate quality assurance program for the software development. The ability of digital systems to detect impending failures and initiate a fail-safe action, is a significant safety issue that should be of special interest to every US utility as well as to the US Nuclear Regulatory Commission. 12 refs. 5 tabs

  18. Advanced thermionic nuclear electric propulsion for LEO to GEO transfer in 14 days

    International Nuclear Information System (INIS)

    Advanced thermionic nuclear power supplies can be designed for extraordinary performance for short lifetime applications. This could enable electric propulsion for use on orbital tugs with a transfer time of two weeks or less, rather than 150 to 200 days as in the traditional approach. Payloads in excess of 17,000 kg are possible in geosynchronous orbit, far in excess of the capability of the existing Space Shuttle Upper Stage

  19. Dynamic Behavior of Hybrid APM (Advanced Pore Morphology Foam) and Aluminum Foam Filled Structures

    OpenAIRE

    Joerg Weise; Valerio Mussi; Michele Monno; Massimo Goletti; Joachim Baumeister

    2012-01-01

    The aim of this work is to evaluate the effect of different densities of hybrid aluminum polymer foam on the frequency behavior of a foam filled steel structure with different ratios between steel and foam masses. The foam filled structure is composed of three steel tubes with a welded flange at both ends bolted together to form a portal grounded by its free ends. Structure, internal and ground constraints have been designed and manufactured in order to minimize nonlinear effects and to guara...

  20. A MICROFLUIDIC MAGNETIC HYBRID ACTUATOR FOR ADVANCED HANDLING FUNCTIONS AT CELL RESOLUTION

    OpenAIRE

    Fouet, Marc; Courson, Rémi; Dollat, Xavier; Medale, Daniel; Gué, Anne-Marie

    2014-01-01

    In microfluidics, the use of super-paramagnetic microparticles (SMPs) has experienced a dramatic increase over the last decade, but control of the magnetic field at micro scale is still a topical issue. Permanent magnets don't offer a programmable approach, external coils require a certain power, and neither are usually integrated. Hybrid systems, which include external magnets to generate a high and homogeneous magnetic field, and integrated coils that produce a high gradient, are seemingly ...

  1. Dynamic Behavior of Hybrid APM (Advanced Pore Morphology Foam and Aluminum Foam Filled Structures

    Directory of Open Access Journals (Sweden)

    Joerg Weise

    2012-06-01

    Full Text Available The aim of this work is to evaluate the effect of different densities of hybrid aluminum polymer foam on the frequency behavior of a foam filled steel structure with different ratios between steel and foam masses. The foam filled structure is composed of three steel tubes with a welded flange at both ends bolted together to form a portal grounded by its free ends. Structure, internal and ground constraints have been designed and manufactured in order to minimize nonlinear effects and to guarantee optimal constraint conditions. Mode shapes and frequencies were verified with finite elements models (FEM to be in the range of experimental modal analysis, considering the frequency measurement range limits for instrumented hammer and accelerometer. Selected modes have been identified with suitable modal parameters extraction techniques. Each structure has been tested before and after filling, in order to compute the percentage variation of modal parameters. Two different densities of hybrid aluminum polymer foam have been tested and compared with structures filled with aluminum foams produced using the powder compact melting technique. All the foam fillings were able to suppress high frequency membrane modes which results in a reduction of environmental noise and an increase in performance of the components. Low frequency modes show an increase in damping ratio only when small thickness steel frames are filled with either Hybrid APM or Alulight foam.

  2. An advanced nuclear power plant for heavy oil exploitation in the Venezuelan Orinoco oil belt

    International Nuclear Information System (INIS)

    The most important characteristics of the Orinoco Oil Belt (OOB) and of its heavy oil content, together with the main requirements for its exploitation, are presented here for analyzing the possibilities of the application of advanced nuclear power as main energy source in the heavy oil exploitation in the OOB. A steamsupply advanced nuclear cogeneration plant based on high temperature reactors is suggested for both the extraction and upgrading of the crude oil. The model consists of a plant for a 100 km2 oil field producing 100.000 barrels per day of refinery ready synthetic oil during 25 years. Three 1200 MW(th) reactors, built successively, supply a great portion of the required process heat, injection steam and electricity. Steam conditions are: for the process heat, a maximum pressure of 10 MPa at a temperature of 500deg C, and, for the injection steam, pressures between 12 and 17 MPa at saturation temperatures. Clear advantages for an advanced nuclear option application in the OOB development are substantiated, and a feasibility study is recommended. (orig.)

  3. Nuclear-Driven Copper-Based Hybrid Thermo/Electro Chemical Cycle for Hydrogen Production

    International Nuclear Information System (INIS)

    the applicability of high-temperature nuclear reactors as an ideal fit to providing thermal energy and electricity required for operating the hybrid thermochemical plant with high overall system efficiency. (authors)

  4. Taking the perfect nuclear image: quality control, acquisition, and processing techniques for cardiac SPECT, PET, and hybrid imaging.

    Science.gov (United States)

    Case, James A; Bateman, Timothy M

    2013-10-01

    Nuclear Cardiology for the past 40 years has distinguished itself in its ability to non-invasively assess regional myocardial blood flow and identify obstructive coronary disease. This has led to advances in managing the diagnosis, risk stratification, and prognostic assessment of cardiac patients. These advances have all been predicated on the collection of high quality nuclear image data. National and international professional societies have established guidelines for nuclear laboratories to maintain high quality nuclear cardiology services. In addition, laboratory accreditation has further advanced the goal of the establishing high quality standards for the provision of nuclear cardiology services. This article summarizes the principles of nuclear cardiology single photon emission computed tomography (SPECT) and positron emission tomography (PET) imaging and techniques for maintaining quality: from the calibration of imaging equipment to post processing techniques. It also will explore the quality considerations of newer technologies such as cadmium zinc telleride (CZT)-based SPECT systems and absolute blood flow measurement techniques using PET. PMID:23868070

  5. Development of technetium alloy waste forms for advanced nuclear energy cycles

    International Nuclear Information System (INIS)

    The Fuel Cycle Technologies (FCT) Program within the Office of Nuclear Energy of the U.S. Department of Energy is charged with developing nuclear fuel cycle options that improve use of actinide resources, responsibly manage wastes, improve and limit proliferation risk. Technetium is a fission product of particular concern for disposal in a repository because of its high fission yield, long half-life, and high solubility and mobility in groundwater as pertechnetate. For example, modeling studies for the former Yucca Mountain repository site indicated that technetium would be an important dose contributor after closure of the repository, in the first 10,000 years. The FCT Program is investigating a range of potential repository environments for ultimate disposal of fission products including technetium from advanced nuclear fuel recycling schemes

  6. Study and development of advanced control techniques for nuclear reactors and robots

    Energy Technology Data Exchange (ETDEWEB)

    March-Leuba, C.

    1989-08-01

    This report studies and develops some aspects of the optimal control theory with the objective of evaluating benefits that the nuclear industry could obtain by applying advanced control techniques. First, the basic relationship between optimal control theory and closed-loop control design has been identified. As a result of this work, new algorithms have been developed for feedback implementations. The applicability of these new algorithms to problems such as state estimation, filtering, model update, and model decoupling has been studied. In addition, new alternatives to control design that are not based on optimal control theory have been developed. A broad range of application examples has been presented for several physical systems, including pressurized water nuclear reactors, boiling water nuclear reactors, steam generators, and robotics. 22 refs., 26 figs.

  7. Study and development of advanced control techniques for nuclear reactors and robots

    International Nuclear Information System (INIS)

    This report studies and develops some aspects of the optimal control theory with the objective of evaluating benefits that the nuclear industry could obtain by applying advanced control techniques. First, the basic relationship between optimal control theory and closed-loop control design has been identified. As a result of this work, new algorithms have been developed for feedback implementations. The applicability of these new algorithms to problems such as state estimation, filtering, model update, and model decoupling has been studied. In addition, new alternatives to control design that are not based on optimal control theory have been developed. A broad range of application examples has been presented for several physical systems, including pressurized water nuclear reactors, boiling water nuclear reactors, steam generators, and robotics. 22 refs., 26 figs

  8. Study on advanced nuclear fuel cycle of PWR/CANDU synergism

    International Nuclear Information System (INIS)

    According to the concrete condition that China has both PWR and CANDU reactors, one of the advanced nuclear fuel cycle strategy of PWR/CANDU synergism ws proposed, i.e. the reprocessed uranium of spent PWR fuel was used in CANDU reactor, which will save the uranium resource, increase the energy output, decrease the quantity of spent fuels to be disposed and lower the cost of nuclear power. Because of the inherent flexibility of nuclear fuel cycle in CANDU reactor, the transition from the natural uranium to the recycled uranium (RU) can be completed without any changes of the structure of reactor core and operation mode. Furthermore, because of the low radiation level of RU, which is acceptable for CANDU reactor fuel fabrication, the present product line of fuel elements of CANDU reactor only need to be shielded slightly, also the conditions of transportation, operation and fuel management need not to be changed. Thus this strategy has significant practical and economical benefit

  9. Brayton Power Conversion System Study to Advance Technology Readiness for Nuclear Electric Propulsion — Phase I

    Science.gov (United States)

    Frye, Patrick E.; Allen, Robert; Delventhal, Rex

    2005-02-01

    To investigate and mature space based nuclear power conversion technologies NASA awarded several contracts under Prometheus, the Nuclear Systems Program. The studies described in this paper were performed under one of those contracts, which was to investigate the use of a nuclear power conversion system based on the closed Brayton cycle (CBC). The conceptual design effort performed included BPCS (Brayton power conversion system) trade studies to minimize system weight and radiator area and advance the state of the art of BPCS technology. The primary requirements for studies were a power level of 100 kWe (to the PPU), a low overall power system mass (with a target of less than 3000 kg), and a lifetime of 15 years (10 years full power). For the radiation environment, the system was to operate in the generic space environment and withstand the extreme environments within the Jovian system. The studies defined a BPCS design traceable to NBP (Nuclear Electric Propulsion) requirements and suitable for future potential missions with a sound technology plan for TRL (Technical Readiness Level) advancement identified. The studies assumed a turbine inlet temperature ˜ 100C above the current the state of the art capabilities with materials issues identified and an approach for resolution developed. Analyses and evaluations of six HRS (heat rejection subsystem) concepts and PMAD (Power Management and Distribution) architecture trades will be discussed in the paper.

  10. Perspective on Advances in Resonance-Region Nuclear Modeling and Opportunities for Future Research

    International Nuclear Information System (INIS)

    The advent of high-fidelity radiation-transport modeling capabilities, coupled with the need to analyze complex nuclear systems, has served to emphasize the importance of high-precision cross section data, including the associated covariance information. Due to the complex nature of resonance-region interactions, cross section data cannot be calculated directly from theory; rather, high-precision resonance-region cross section measurements must be made at facilities such as the Oak Ridge Electron Linear Accelerator (ORELA) at Oak Ridge National Laboratory (ORNL), Geel Electron Linear Accelerator (GELINA), Rensselaer Polytechnic Institute (RPI). To extract accurate cross section data from these measurements, detailed nuclear modeling of the measured data is performed to parameterize the cross section behavior in the resonance range. The objective of this paper is to highlight recent advances in resonance-region nuclear modeling with particular emphasis on the covariance analysis capabilities. Opportunities for future research are identified in an effort to stimulate further advances in the state of the art nuclear modeling capabilities.

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

    International Nuclear Information System (INIS)

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

  12. Application of a structural model for advanced analysis in the evaluation of nuclear safety

    International Nuclear Information System (INIS)

    The Advanced Analysis concept, which means the direct consideration of both physical and geometric nonlinear effects in the analysis and design of steel buildings structures, represents the state-of-art in the field of structural analysis by this beginning of the 21 st century. In this context, the present paper presents an Advanced Analysis methodology applied to the Safety Evaluation of high hazardous civil structures. This Safety Evaluation plays an important part in the regulators position as a step in the licensing process performed by CNEN - Brazilian Nuclear Energy Commission. The proposed Advance Analysis procedure is implemented by a refined second-order plastic hinge model. The application of this model allows to carry out: the description of the inelastic structural behavior; the identification of the collapse mechanism; the ultimate load level; structural safety's level and the service ability limit. (author)

  13. Radiation Damage in Nuclear Fuel for Advanced Burner Reactors: Modeling and Experimental Validation

    Energy Technology Data Exchange (ETDEWEB)

    Jensen, Niels Gronbech; Asta, Mark; Ozolins, Nigel Browning' Vidvuds; de Walle, Axel van; Wolverton, Christopher

    2011-12-29

    The consortium has completed its existence and we are here highlighting work and accomplishments. As outlined in the proposal, the objective of the work was to advance the theoretical understanding of advanced nuclear fuel materials (oxides) toward a comprehensive modeling strategy that incorporates the different relevant scales involved in radiation damage in oxide fuels. Approaching this we set out to investigate and develop a set of directions: 1) Fission fragment and ion trajectory studies through advanced molecular dynamics methods that allow for statistical multi-scale simulations. This work also includes an investigation of appropriate interatomic force fields useful for the energetic multi-scale phenomena of high energy collisions; 2) Studies of defect and gas bubble formation through electronic structure and Monte Carlo simulations; and 3) an experimental component for the characterization of materials such that comparisons can be obtained between theory and experiment.

  14. Heavy Liquid Metal Corrosion of Structural Materials in Advanced Nuclear Systems

    Science.gov (United States)

    Caro, M.; Woloshun, K.; Rubio, F.; Maloy, S. A.; Hosemann, P.

    2013-08-01

    Interest in advanced nuclear concepts using liquid metal coolant has increased in the past few years. Liquid metal coolants have been proposed for the next generation of small-sized nuclear reactors, which offer exceptional safety and reliability, sustainability, nonproliferation, and economic competitiveness. Heavy liquid metal coolants are investigated for advanced fast reactors that operate at high temperatures, reaching high efficiencies. Lead and lead-bismuth eutectic (LBE) coolants are also proposed as coolants and targets of accelerator driven systems. High temperature, corrosive environment, high fast neutron flux, high fluence, and radiation damage, among other physical phenomena, challenge the integrity of materials in these advanced systems. Excellent compatibility with the liquid coolant is recognized as a key factor in the selection of structural materials for advanced concepts. In this article, we review materials requirements for heavy metal cooled systems with emphasis on lead and LBE materials corrosion properties. We describe experimental corrosion tests currently ongoing at the Los Alamos National Laboratory (LANL) Development of Lead Alloy Technical Applications (DELTA) loop. DELTA is a facility designed to study the long-term corrosive effects of LBE on structural materials under relevant conditions of chemistry, flow, and temperature. The research studies will provide data of corrosion rates and corrosion mechanisms in selected steel exposed to high velocity (above 2 m/s) in flowing LBE at 500°C. Fundamental research studies will help support conceptual design efforts and further the development of heavy liquid metals technology.

  15. New advanced small and medium nuclear power reactors: possible nuclear power plants for Australia

    International Nuclear Information System (INIS)

    In recent years interest has increased in small and medium sized nuclear power reactors for generating electricity and process heat. This interest has been driven by a desire to reduce capital costs, construction times and interest during construction, service remote sites and ease integration into small grids. The IAEA has recommended that the term 'small' be applied to reactors with a net electrical output less than 300 MWe and the term 'medium' to 300-700 MWe. A large amount of experience has been gained over 50 years in the design, construction and operation of small and medium nuclear power reactors. Historically, 100% of commercial reactors were in these categories in 1951-1960, reducing to 21% in 1991-2000. The technologies involved include pressurised water reactors, boiling water reactors, high temperature gas-cooled reactors, liquid metal reactors and molten salt reactors. Details will be provided of two of the most promising new designs, the South African Pebble Bed Modular Reactor (PBMR) of about 110 MWe, and the IRIS (International Reactor Innovative and Secure) reactor of about 335 MWe. Their construction costs are estimated to be about US$l,000/kWe with a generating cost for the PBMR of about US1.6c/kWh. These costs are lower than estimated for the latest designs of large reactors such as the European Pressurised Reactor (EPR) designed for 1,600 MWe for use in Europe in the next decade. It is concluded that a small or medium nuclear power reactor system built in modules to follow an increasing demand could be attractive for generating low cost electricity in many Australian states and reduce problems arising from air pollution and greenhouse gas emissions from burning fossil fuels

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

    International Nuclear Information System (INIS)

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

  17. Thermodynamic analysis of energy conversion and transfer in hybrid system consisting of wind turbine and advanced adiabatic compressed air energy storage

    International Nuclear Information System (INIS)

    A simulation model consisting of wind speed, wind turbine and AA-CAES (advanced adiabatic compressed air energy storage) system is developed in this paper, and thermodynamic analysis on energy conversion and transfer in hybrid system is carried out. The impacts of stable wind speed and unstable wind speed on the hybrid system are analyzed and compared from the viewpoint of energy conversion and system efficiency. Besides, energy conversion relationship between wind turbine and AA-CAES system is investigated on the basis of process analysis. The results show that there are several different forms of energy in hybrid system, which have distinct conversion relationship. As to wind turbine, power coefficient determines wind energy utilization efficiency, and in AA-CAES system, it is compressor efficiency that mainly affects energy conversion efficiencies of other components. The strength and fluctuation of wind speed have a direct impact on energy conversion efficiencies of components of hybrid system, and within proper wind speed scope, the maximum of system efficiency could be expected. - Highlights: • A hybrid system consisting of wind, wind turbine and AA-CAES system is established. • Energy conversion in hybrid system with stable and unstable wind speed is analyzed. • Maximum efficiency of hybrid system can be reached within proper wind speed scope. • Thermal energy change in hybrid system is more sensitive to wind speed change. • Compressor efficiency can affect other efficiencies in AA-CAES system

  18. The U.S. nuclear future: DOE initiatives to advance nuclear energy in the United States

    International Nuclear Information System (INIS)

    Also under the impact of the events on September 11, 2001, the United States regards long-term, reliable planning for the future structure of the country's energy supply an important activity to be addressed by all parties involved in politics, industry, and research. In the light of the existing resource situation, the importance of reliable energy supply, and the necessary protection of the environment and the world climate, a balanced interaction is sought of energy, ecology, and economy. The special objectives pursued include increased efficiency in energy use and energy conservation, modernization of the infrastructure in the energy sector, and diversification of energy supply. The structure of the US power plant park and the expected increases in electricity consumption are likely to give rise to the need to add approximately 390,000 to 570,000 MW of new generating capacity over the next twenty years. In this connection, nuclear power is expected to play an important role as a safe, non-polluting, economic source of energy. The Department of Energy therefore also supports initiatives seeking to extend the licenses of existing nuclear power plants and to promote research and development of future 4th generation reactors in national and international programs. In addition, work is supported which deals, e.g., with matters of transmutation, the repository storage of radioactive residues, and the implementation of safeguards measures. (orig.)

  19. FY2001 Final Report Laboratory Directed Research and Development (LDRD) on Advanced Nuclear Fuel Design in the Future Nuclear Energy Market

    Energy Technology Data Exchange (ETDEWEB)

    Christensen, D.; Choi, J.-S.; DiSabatino, A.; Wirth, B.

    2001-09-30

    This study is to research the maturity of advanced nuclear fuel and cladding technology and to explore the suitability of existing technology for addressing the emerging requirements for Generation IV reactors and emerging thermal/fast spectrum reactors, while simultaneously addressing nuclear waste management, and proliferation resistance concerns.

  20. Hybrid Modeling for Scenario-Based Evaluation of Failure Effects in Advanced Hardware-Software Designs

    Science.gov (United States)

    Malin, Jane T.; Fleming, Land; Throop, David

    2001-01-01

    This paper describes an incremental scenario-based simulation approach to evaluation of intelligent software for control and management of hardware systems. A hybrid continuous/discrete event simulation of the hardware dynamically interacts with the intelligent software in operations scenarios. Embedded anomalous conditions and failures in simulated hardware can lead to emergent software behavior and identification of missing or faulty software or hardware requirements. An approach is described for extending simulation-based automated incremental failure modes and effects analysis, to support concurrent evaluation of intelligent software and the hardware controlled by the software