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Sample records for aps reactor

  1. The AP1000 reactor

    International Nuclear Information System (INIS)

    The design of the AP1000 reactor began 20 years ago when Westinghouse launched the AP600 reactor project. In fact by re-assessing AP600's safety margins Westinghouse realized that the its power output could be raised without putting at risk its safety standard. The AP1000 was born, it yields 1100 MWe. The main AP1000's design features is its passive safety (particularly after the Fukushima accident) and its modularity. The passive safety of the AP1000 implies: -) no humane intervention needed for 72 hours at least after the incident; -) no necessity for redundant complex safety systems. The modularity means that the plant, the reactor and other buildings are constructed from a choice of 300 modular units. These units can be built off-site and fit together on site. The modularity allows more construction activities to be led simultaneously and more chances to cope with the construction schedule. The NRC has approved the operation license for 30 years of the first AP1000 being built in the Usa (Vogtle plant in Georgia). 4 AP1000 are being built in China (Sanmen and Haiyang sites) and 6 others are planned in the Usa. Westinghouse is convinced that the AP1000's passive safety makes it more attractive. Let us not forget that Westinghouse was at the origin of the concept of pressurized water reactors, an idea adopted for half the nuclear power stations in the world and for all the plants now active in France. (A.C.)

  2. Identification number system of AP1000 pressurized water reactor and its application

    International Nuclear Information System (INIS)

    The coding system of a power plant is closely related to the type and the construction mode of the nuclear reactor. Since AP1000 pressurized water reactor has been constructed in Sanmen Nuclear Power Project for the first time, it is important to learn this System. This paper introduces the operational rules of AP1000 coding system and shows some cases how it works in Sanmen nuclear power project, so that we can learnt more about it, improve it while promoting the application of the AP1000 technologies, and revise it based on the actual conditions of China. (authors)

  3. The Westinghouse AP1000 plant design: a generation III+ reactor with unique proven passive safety technology

    International Nuclear Information System (INIS)

    The AP1000 plant is an 1100-M We pressurized water reactor with passive safety features and extensive plant simplifications and standardization that simplify construction, operation, maintenance, safety, and cost. The AP1000 plant is based on proven pressurized water reactor (PWR) technology, with an emphasis on safety features that rely solely on natural forces. These passive safety features are combined with simple, active, defense-in-depth systems used during normal plant operations which also provide the first level of defense against more probable events. This paper focuses on specific safety and licensing topics: the AP1000 plant robustness to be prepared for extreme events that may lead to catastrophic loss of infrastructure, such as the Fukushima Dai-ichi event, and the AP1000 plant compliance with the safety objectives for new plants. The first deployment of the AP1000 plant formally began in July 2007 when Westinghouse Electric Company and its consortium partner, the Shaw Group, signed contracts for four AP1000 units on coastal sites of Sanmen and Haiyang, China. Both sites have the planned ability to accommodate at least six AP1000 units; construction is largely concurrent for all four units. Additionally, the United States (U.S.) Nuclear Regulatory Commission (NRC) issued combined licenses (COLs) to allow Southern Nuclear Operating Company (SNC) and South Carolina Electric and Gas Company (SCE and G) to construct and operate AP1000 plants. Within this paper, the various factors that contribute to an unparalleled level of design, construction, delivery, and licensing certainty for any new AP1000 plant projects are described. These include: 1) How the AP1000 plant design development and reviews undertaken in the United States, China and Europe increase licensing certainty. 2) How the AP1000 passive plant robustness against extreme events that result in large loss of infrastructure further contributes to the licensing certainty in a post

  4. The Westinghouse AP1000 plant design: a generation III+ reactor with unique proven passive safety technology

    Energy Technology Data Exchange (ETDEWEB)

    Demetri, K. J.; Leipner, C. I.; Marshall, M. L., E-mail: demetrkj@westinghouse.com [Westinghouse Electric Company, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

    2015-09-15

    The AP1000 plant is an 1100-M We pressurized water reactor with passive safety features and extensive plant simplifications and standardization that simplify construction, operation, maintenance, safety, and cost. The AP1000 plant is based on proven pressurized water reactor (PWR) technology, with an emphasis on safety features that rely solely on natural forces. These passive safety features are combined with simple, active, defense-in-depth systems used during normal plant operations which also provide the first level of defense against more probable events. This paper focuses on specific safety and licensing topics: the AP1000 plant robustness to be prepared for extreme events that may lead to catastrophic loss of infrastructure, such as the Fukushima Dai-ichi event, and the AP1000 plant compliance with the safety objectives for new plants. The first deployment of the AP1000 plant formally began in July 2007 when Westinghouse Electric Company and its consortium partner, the Shaw Group, signed contracts for four AP1000 units on coastal sites of Sanmen and Haiyang, China. Both sites have the planned ability to accommodate at least six AP1000 units; construction is largely concurrent for all four units. Additionally, the United States (U.S.) Nuclear Regulatory Commission (NRC) issued combined licenses (COLs) to allow Southern Nuclear Operating Company (SNC) and South Carolina Electric and Gas Company (SCE and G) to construct and operate AP1000 plants. Within this paper, the various factors that contribute to an unparalleled level of design, construction, delivery, and licensing certainty for any new AP1000 plant projects are described. These include: 1) How the AP1000 plant design development and reviews undertaken in the United States, China and Europe increase licensing certainty. 2) How the AP1000 passive plant robustness against extreme events that result in large loss of infrastructure further contributes to the licensing certainty in a post

  5. Report of the APS Neutrino Study Reactor Working Group

    Energy Technology Data Exchange (ETDEWEB)

    Abouzaid, E.; Anderson, K.; Barenboim, G.; Berger, B.; Blucher, E.; Bolton, T.; Choubey, S.; Conrad, J.; Formaggio, J.; Freedman, S.; Finely, D.; Fisher, P.; Fujikawa, B.; Gai, M.; Goodman, M.; de Goueva, A.; Hadley, N.; Hahn, R.; Horton-Smith, G.; Kadel, R.; Kayser, B.; Heeger, K.; Klein, J.; Learned, J.; Lindner, M.; Link, J.; Luk, K.-B.; McKeown, R.; Mocioiu, I.; Mohapatra, R.; Naples, D.; Peng, J.; Petcov, S.; Pilcher, J.; Rapidis, P.; Reyna, D.; Shaevitz, M.; Shrock, R.; Stanton, N.; Stefanski, R.; Yamamoto, R.; Worcester, M.

    2004-10-28

    The worldwide program to understand neutrino oscillations and determine the neutrino mixing parameters, CP violating effects, and mass hierarchy will require a broad combination of measurements. The group believes that a key element of this future neutrino program is a multi-detector neutrino experiment (with baselines of {approx} 200 m and {approx} 1.5 km) with a sensitivity of sin{sup 2} 2{theta}{sub 13} = 0.01. In addition to oscillation physics, the reactor experiment may provide interesting measurements of sin{sup 2} {theta}{sub W} at Q{sup 2} = 0, neutrino couplings, magnetic moments, and mixing with sterile neutrino states. {theta}{sub 13} is one of the twenty-six parameters of the standard model, the best model of electroweak interactions for energies below 100 GeV and, as such, is worthy of a precision measurement independent of other considerations. A reactor experiment of the proposed sensitivity will allow a measurement of {theta}{sub 13} with no ambiguities and significantly better precision than any other proposed experiment, or will set limits indicating the scale of future experiments required to make progress. Figure 1 shows a comparison of the sensitivity of reactor experiments of different scales with accelerator experiments for setting limits on sin{sup 2} 2{theta}{sub 13} if the mixing angle is very small, or for making a measurement of sin{sup 2} 2{theta}{sub 13} if the angle is observable. A reactor experiment with a 1% precision may also resolve the degeneracy in the {theta}{sub 23} parameter when combined with long-baseline accelerator experiments. In combination with long-baseline measurements, a reactor experiment may give early indications of CP violation and the mass hierarchy. The combination of the T2K and Nova long-baseline experiments will be able to make significant measurements of these effects if sin{sup 2} 2{theta}{sub 13} > 0.05 and with enhanced beam rates can improve their reach to the sin{sup 2} 2{theta}{sub 13} > 0.02 level

  6. Analysis of N-16 concentration in primary cooling system of AP1000 power reactor

    Science.gov (United States)

    Rohanda, Anis; Waris, Abdul

    2015-04-01

    Nitrogen-16 (N-16) is one of the radiation safety parameter on the primary reactor system. The activation product, N-16, is the predominant contributor to the activity in the reactor coolant system during reactor operation. N-16 is activation product derived from activation of O-16 with fast neutron based on 16O(n,p)16N reaction. Thus study is needed and it performs to determine N-16 concentration in reactor coolant (primary coolant) in supporting radiation safety. One of the way is using analytical methode based on activation and redecay princip to obtain N-16 concentration. The analysis was performed on the configuration basis and operational of Westinghouse AP1000 power reactor in several monitoring points at coolant reactor system. The results of the calculation of N-16 concentration at the core outlet, reactor vessel outlet, pressurizer line, inlet and outlet of steam generators, primary pumps, reactor vessels inlet and core inlet are: 281, 257, 255, 250, 145, 142, 129 and 112 µCi/gram respectively. The results of analysis compared with AP1000 design control document as standard values. The verification showed very high accuracy comparation between analytical results and standard values.

  7. Analysis of N-16 concentration in primary cooling system of AP1000 power reactor

    International Nuclear Information System (INIS)

    Nitrogen-16 (N-16) is one of the radiation safety parameter on the primary reactor system. The activation product, N-16, is the predominant contributor to the activity in the reactor coolant system during reactor operation. N-16 is activation product derived from activation of O-16 with fast neutron based on 16O(n,p)16N reaction. Thus study is needed and it performs to determine N-16 concentration in reactor coolant (primary coolant) in supporting radiation safety. One of the way is using analytical methode based on activation and redecay princip to obtain N-16 concentration. The analysis was performed on the configuration basis and operational of Westinghouse AP1000 power reactor in several monitoring points at coolant reactor system. The results of the calculation of N-16 concentration at the core outlet, reactor vessel outlet, pressurizer line, inlet and outlet of steam generators, primary pumps, reactor vessels inlet and core inlet are: 281, 257, 255, 250, 145, 142, 129 and 112 µCi/gram respectively. The results of analysis compared with AP1000 design control document as standard values. The verification showed very high accuracy comparation between analytical results and standard values

  8. Reactor coolant pump type RUV for Westinghouse Electric Company LLC reactor AP1000 TM

    International Nuclear Information System (INIS)

    The RUV is a reactor coolant pump, specially designed for the Westinghouse Electric Company LLC AP1000 TM reactor. It is a hermetically sealed, wet winding motor pump. The RUV is a very compact, vertical pump/motor unit, designed to fit into the compartment next to the reactor pressure vessel. Each of the two steam generators has two pump casings welded to the channel head by the suction nozzle. The pump/motor unit consists of a pump part, where a semi-axial impeller/diffuser combination is mounted in a one-piece pump casing. Computational Fluid Dynamics methods combined with various hydraulic tests in a 1:2 scale hydraulic test assure full compliance with the specific customer requirements. A short and rigid shaft, supported by a radial bearing, connects the impeller with the high inertia flywheel. This flywheel consists of a one-piece forged stainless steel cylinder, with an option for several smaller heavy metal cylinders inside. The flywheel is located inside the thermal barrier, which forms part of the pressure boundary. A specific arrangement of cooling water circuits guarantees a homogeneous temperature distribution in and around the flywheel, minimizes the friction losses of the flywheel and protects the motor from hot coolant. The driving torque is transmitted by the motor shaft, which itself is supported by two radial bearings. A three-phase, high-voltage squirrel-cage induction motor generates the driving torque. Due to the wet winding concept it is possible to achieve positive effects regarding motor lifetime. The cooling water is forced through the stator windings and the gap between rotor and stator by an auxiliary impeller. Furthermore, this wet winding motor concept has higher efficiency as compared to a canned motor since there are no eddy current losses. As part of the design process and in addition to the hydraulic scale model, a complete half scale model pump was built. It was used to verify the calculations performed like coast

  9. Displacement damage effects on CMOS APS image sensors induced by neutron irradiation from a nuclear reactor

    OpenAIRE

    Zujun Wang; Shaoyan Huang; Minbo Liu; Zhigang Xiao; Baoping He; Zhibin Yao; Jiangkun Sheng

    2014-01-01

    The experiments of displacement damage effects on CMOS APS image sensors induced by neutron irradiation from a nuclear reactor are presented. The CMOS APS image sensors are manufactured in the standard 0.35 μm CMOS technology. The flux of neutron beams was about 1.33 × 108 n/cm2s. The three samples were exposed by 1 MeV neutron equivalent-fluence of 1 × 1011, 5 × 1011, and 1 × 1012 n/cm2, respectively. The mean dark signal (KD), dark signal spike, dark signal non-uniformity (DSNU), noise (VN)...

  10. Probabilistic Safety Assessment (PSA) Level 1 Seismic Condition for AP600 Power Reactor

    International Nuclear Information System (INIS)

    Research about probabilistic safety assessment level 1 for AP600 power reactor has been conducted an seismic condition as external initiator. They key elements of this research are seismic fragility evaluation to define fragility curve of component s, accident sequence analysis to build event tree and fault tree, and core damage frequency as the final result. The seismic hazard analysis products a seismic occurrence per year for a certain range of seismic acceleration on a certain location. With large break LOCA as an addition fault condition 10 components and systems of AP600 have been chosen whose fragility curves can be made. Those are reactor coolant system piping. reactor protection system, reactor coolant pump, core makeup tank, accumulator tank, RWST, DC distribution panel cable trays, check valve, and isolation valve. The fragility curve shows in conditional fault probability on a seismic condition in form of normal cumulative distribution function with different confidences. This function is integrated from median acceleration Am, uncertainty βu and randomness βr parameter. From function and response analysis of AP600 systems a specific event tree and fault tree for large break LOCA are built with the fault probability parameter from the fragility curves as the input. The conditional probability of core damage can therefore be calculated for each accident sequence. After combined with values of the seismic hazard curve the core damage frequency per year for for each accident sequence and totally are obtained. The final calculation shows that the total core damage frequency for AP600 power reactor on seismic condition with the initiated fault condition large break LOCA is 3,87.10-7/years

  11. Analysis and application of a simulator of a nuclear reactor AP-600; Analisis y aplicacion de un simulador de un reactor nuclear AP-600

    Energy Technology Data Exchange (ETDEWEB)

    Medina S, V. S. [UNAM, Facultad de Ingenieria, Circuito Interior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Salazar S, E., E-mail: medina_victor@comunidad.unam.mx [UNAM, Facultad de Ingenieria, Division de Ingenieria Electrica, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, 62250 Jiutepec, Morelos (MX)

    2011-11-15

    In front of the resurgence of interest in the nuclear power production, several national organizations have considered convenient to have highly specialized human resources in the technologies of nuclear reactors of III + and IV generation. For this task, the intensive and extensive applications of the computation should been considered, as the virtual instrumentation. The present work analyzes the possible applications of a nuclear simulator provided by the IAEA with base in the design of the reactor AP-600, using a focusing of modular model developed in FORTRAN. One part of the work that was made with the simulator includes the evaluation of 21 transitory events of operation, including the recreation of the accident happened in the nuclear power plant of Three Mile Island in 1979, comparing the actions flow and the answer of the systems under the intrinsic security of a III + generation reactor. The impact that had the mentioned accident was analyzed in the growing of the nuclear energy sector and in the public image with regard to the nuclear power plants. An application for this simulator was proposed, its use as tool for the instruction in the nuclear engineering courses using it to observe the operation of the different security systems and its interrelation inside the power plant as well as a theoretical/practical approach for the student. (Author)

  12. Dynamic simulation and study of Mechanical Shim (MSHIM) core control strategy for AP1000 reactor

    International Nuclear Information System (INIS)

    Highlights: • A reactor core fast simulation program RCFSP is developed for AP1000. • A nodal core model and the MSHIM control strategy are implemented in RCFSP. • Load follow results for the original and revised MSHIM strategies are given. • Parameter sensitivity analysis and optimization of MSHIM control system are performed. - Abstract: The advanced Mechanical Shim (MSHIM) core control strategy is implemented in the AP1000 reactor by a digital rod control system. This control system comprises of two separate rod controllers that automatically control the core reactivity and axial power distribution using the gray and black M control banks and the axial offset (AO) control bank respectively. It has been demonstrated that the MSHIM control system can provide superior reactor control capabilities via automatic rod control only, which needs it to take more burdens than many other traditional core control systems during load change transients. This paper presents the dynamic simulation, and the parameter sensitivity analysis and optimization of the MSHIM control system for AP1000 reactor. A nodal core model is used to describe the dynamic behavior of the reactor core first. Then the nodal model and the original and revised MSHIM strategies are implemented in the AP1000 reactor to develop a fast simulation program in MATLAB/SIMULINK. Based on the simulation program, the MSHIM load follow and load regulation operations are simulated, the results of which demonstrate that the core reactivity and axial power distribution can be well-controlled via automatic rod control only. To show the effects of key factors on the control system behavior, the MSHIM load follow simulations with different control parameter values are performed. According to the simulation results and subsequent quantitative analysis, the mechanisms by which the key factors affect the control system behavior are illustrated and the optimum numerical ranges of these parameters are obtained. These

  13. 77 FR 74696 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on AP-1000...

    Science.gov (United States)

    2012-12-17

    ... published in the Federal Register on October 18, 2012, (77 FR 64146- 64147). Detailed meeting agendas and... COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on AP-1000; Notice of Meeting The ACRS Subcommittee on AP-1000 will hold a meeting on January 18, 2013, Room...

  14. AP1000R pressurised water reactor project in china advances toward completion

    International Nuclear Information System (INIS)

    The AP1000R pressurised water reactor (PWR) project in China is the first deployment of its first-of-a-kind Generation III+ technology, making it one of most internationally important and industry-significant new build projects. The innovative AP1000 PWR design contains advanced passive safety and performance features that involve fewer active safety components than a traditional plant, thereby reducing the site footprint. The AP1000 reactor is the first and only Generation III+ nuclear power plant to be granted design certification by the United States Nuclear Regulatory Commission, and it has received an Interim Design Acceptance Confirmation from the Office for Nuclear Regulation and an Interim Statement of Design Acceptability from the Environment Agency in the United Kingdom. Construction and testing of dual AP1000 PWR units is currently in progress in each of two coastal sites in the People's Republic of China: Sanmen (Zhejiang Province) and Haiyang (Shandong Province). Since the initial contract award in 2007, the Westinghouse Consortium has worked in concert with the owners to construct the plants using innovative structural and mechanical modules. Uniquely designed plant components and essential instrumentation and control systems have been manufactured, delivered, and installed at the plants. Numerous personnel, including future reactor operators, have been trained at both the Sanmen and Haiyang sites, and technology transfer of technical documents and computer codes is well underway. The commercial operation dates are now nearing for Sanmen Unit 1 and Haiyang Unit 1, the first two units scheduled for completion. Consequently, these units are now in advanced stages of completion and present activities include planning and preparation for pre-operational testing, system turnover, and commissioning leading to fuel load, and eventual commercial operation. These activities are pioneering, in that they have never before been performed for a new build of

  15. Displacement damage effects on CMOS APS image sensors induced by neutron irradiation from a nuclear reactor

    Directory of Open Access Journals (Sweden)

    Zujun Wang

    2014-07-01

    Full Text Available The experiments of displacement damage effects on CMOS APS image sensors induced by neutron irradiation from a nuclear reactor are presented. The CMOS APS image sensors are manufactured in the standard 0.35 μm CMOS technology. The flux of neutron beams was about 1.33 × 108 n/cm2s. The three samples were exposed by 1 MeV neutron equivalent-fluence of 1 × 1011, 5 × 1011, and 1 × 1012 n/cm2, respectively. The mean dark signal (KD, dark signal spike, dark signal non-uniformity (DSNU, noise (VN, saturation output signal voltage (VS, and dynamic range (DR versus neutron fluence are investigated. The degradation mechanisms of CMOS APS image sensors are analyzed. The mean dark signal increase due to neutron displacement damage appears to be proportional to displacement damage dose. The dark images from CMOS APS image sensors irradiated by neutrons are presented to investigate the generation of dark signal spike.

  16. Displacement damage effects on CMOS APS image sensors induced by neutron irradiation from a nuclear reactor

    International Nuclear Information System (INIS)

    The experiments of displacement damage effects on CMOS APS image sensors induced by neutron irradiation from a nuclear reactor are presented. The CMOS APS image sensors are manufactured in the standard 0.35 μm CMOS technology. The flux of neutron beams was about 1.33 × 108 n/cm2s. The three samples were exposed by 1 MeV neutron equivalent-fluence of 1 × 1011, 5 × 1011, and 1 × 1012 n/cm2, respectively. The mean dark signal (KD), dark signal spike, dark signal non-uniformity (DSNU), noise (VN), saturation output signal voltage (VS), and dynamic range (DR) versus neutron fluence are investigated. The degradation mechanisms of CMOS APS image sensors are analyzed. The mean dark signal increase due to neutron displacement damage appears to be proportional to displacement damage dose. The dark images from CMOS APS image sensors irradiated by neutrons are presented to investigate the generation of dark signal spike

  17. A large break pipe accident of the AP600 reactor coolant system (RCS) pressure boundary

    International Nuclear Information System (INIS)

    The large break pipe accident for AP600 has been analyzed. The analysis was done to evaluate the performance of protection system (Reactor Trip followed by Pump Trip) and mitigation system (CMT, ACC and IRWST) of the AP600 in order to limit the maximum fuel element cladding temperature so it does not exceed the acceptance criteria. Based on the accident sequences determined, the simulation was done by using PCTRAN Code. The analysis shows that the peak cladding temperature (PCT) which be reached is 698,8oC in case of cold leg break.This PCT is of course below the regulatory limit of 2200 of (1204oC) in the 10 CFR 50.46

  18. Study on the long-term passive cooling extension of AP1000 reactor

    International Nuclear Information System (INIS)

    The AP1000 with high safety is a generation III pressurized water reactor (PWR), its significant feature is passive safety system. However, its passive cooling can only maintain for 72 h and requires additional support from inside or outside the plant. To solve this problem, this study utilized the WGOTHIC software to calculate and analyze the water inventory in the passive containment cooling water tank under different conditions. the results show that when the cooling water inventory is 6553.78 m3, the AP1000 nuclear power plants can achieve long-term, completely passive cooling without any inside or outside the plant. The same outcomes occur when 65-mm-thick containment wall increases the design pressure rating to 0.6 MPa at the cooling water inventory of 5673 m3. Also, the AP1000 shield building was accordingly improved. An ANSYS analysis of the structural stability of the shield building with a 6000 m3 cooling water inventory confirmed that the new design can meet the requirements of the seismic design and the safe residual heat removal requirements of a large-scale PWR. (authors)

  19. AP1000反应堆厂房总体布置设计分析%Analysis of the Overall Layout Design of AP1 000 Reactor Plant

    Institute of Scientific and Technical Information of China (English)

    薛静; 马强

    2013-01-01

    The general layout design of nuclear power plant is an important stage in the whole design work, plays a decisive role to improve plant safety, economy. This paper introduces designs the overal arrangement in the AP1 000 reactor buildin-g, by analyzing the main characteristics of its layout, reviewes and discusses the design idea in the general arrangement of re-actor buildings, and provides some references for other power plant general layout designs.%核电站的总体布置设计是整个设计工作中的重要阶段,对提高电站的安全性、经济性有着举足轻重的作用。本文对AP1000的反应堆厂房内的总体布置设计进行介绍,通过分析其布置的主要特点,对其在反应堆厂房的总体布置中采取的设计理念进行总结和探讨,为其他电站的厂房总体布置设计提供一定的借鉴和参考。

  20. Analysis of an accident type sbloca in reactor contention AP1000 with 8.0 Gothic code; Analisis de un accidente tipo Sbloca en la contencion del reactor AP1000 con el codigo Gothic 8.0

    Energy Technology Data Exchange (ETDEWEB)

    Goni, Z.; Jimenez Varas, G.; Fernandez, K.; Queral, C.; Montero, J.

    2016-08-01

    The analysis is based on the simulation of a Small Break Loss-of-Coolant-Accident in the AP1000 nuclear reactor using a Gothic 8.0 tri dimensional model created in the Science and Technology Group of Nuclear Fision Advanced Systems of the UPM. The SBLOCA has been simulated with TRACE 5.0 code. The main purpose of this work is the study of the thermo-hydraulic behaviour of the AP1000 containment during a SBLOCA. The transients simulated reveal close results to the realistic behaviour in case of an accident with similar characteristics. The pressure and temperature evolution enables the identification of the accident phases from the RCS point of view. Compared to the licensing calculations included in the AP1000 Safety Analysis, it has been proved that the average pressure and temperature evolution is similar, yet lower than the licensing calculations. However, the temperature and inventory distribution are significantly heterogeneous. (Author)

  1. AP1000® PWR reactor physics analysis with VERA-CS and KENO-VI. Part 2. Power distribution

    International Nuclear Information System (INIS)

    Westinghouse has applied the Core Simulator of the Virtual Environment for Reactor Applications, VERA-CS, under development by the Consortium for Advanced Simulation of LWRs (CASL) to the core physics analysis of the AP1000® PWR. The AP1000 PWR features an advanced first core with radial and axial heterogeneities, including enrichment zoning, multiple burnable absorbers, and a combination of light and heavy control banks to enable the MSHIMTM advanced operational strategy. These advanced features make application of VERA-CS to the AP1000 PWR first core especially relevant to qualify VERA performance. A companion paper at this conference describes the results obtained with VERA-CS and the KENO Monte-Carlo code for startup physics tests simulations of the AP1000 PWR first core (critical boron, rod worth and reactivity coefficients). This paper describes the results of detailed power distribution comparisons between VERA-CS and KENO, and confirms the excellent numerical agreement reported in the companion paper for the startup physics tests simulations. (author)

  2. The effects of annular flow on dynamics of AP1000 reactor coolant pump rotor

    International Nuclear Information System (INIS)

    The feature of AP1000 RCP rotor system is that the whole rotor system is immersed in the annular flow. The rotor in annular flow induces fluctuating fluid forces, thereby causes vibration and noise, even rotor instability. The effects of annular flow on AP1000 RCP rotor system are different from that in bearings and seals and should be considered in a new approach. Based on the turbulent bulk flow theory and perturbation analysis, the rotor-flow coupled linear dynamic model is developed to predict the dynamics of AP1000 RCP immersed rotor. During the analysis, the rotor eccentricity, stator and rotor wall friction effects are emphasized. The analytic results show the rotor eccentricity induces divergence instability and significant decrease of instability speed for system with moderate or large eccentricity; however, stator and rotor wall friction effects distinctly suppress divergence instability and increase instability speed for system with small or moderate eccentricity. Finally, we can have the conclusion that the flow-structure interaction induced by annular flow has great effects on the dynamics of AP1000 RCP immersed rotor, which should be considered in rotor dynamic analysis and design of AP1000 RCP. The method and results in the paper have theoretical significance and practical importance. (author)

  3. The design reliability assurance program for the Westinghouse AP600 reactor

    International Nuclear Information System (INIS)

    The mission of the Westinghouse AP600 is to provide a safe, simple, standardized and economically competitive design with a high degree of operability and ease of maintenance. To meet these goals, the AP600 Reliability, Availability and Maintainability program (RAM) and Design Reliability Assurance Program (D-RAP) were established. These programs, from the outset of the design process, systematically identified the safety and availability goals of the plant, defined the associated performance goals of the plant's critical systems, and provided insights to the design process to improve component reliability. The result is a documented list of risk-significant and availability-significant structures, systems and components (SSCs) whose reliability values must be established during manufacture and maintained throughout the life of the plant. (author)

  4. Combined reactor neutron beam and {sup 60}Co γ-ray radiation effects on CMOS APS image sensors

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Zujun, E-mail: wangzujun@nint.ac.cn; Chen, Wei; Sheng, Jiangkun; Liu, Yan; Xiao, Zhigang; Huang, Shaoyan; Liu, Minbo [State Key Laboratory of Intense Pulsed Radiation Simulation and Effect, Northwest Institute of Nuclear Technology, P.O.Box 69-10, Xi’an, Shaanxi 710024 China (China)

    2015-02-15

    The combined reactor neutron beam and {sup 60}Co γ-ray radiation effects on complementary metal-oxide semiconductor (CMOS) active pixel sensors (APS) have been discussed and some new experimental phenomena are presented. The samples are manufactured in the standard 0.35-μm CMOS technology. Two samples were first exposed to {sup 60}Co γ-rays up to the total ionizing dose (TID) level of 200 krad(Si) at the dose rates of 50.0 and 0.2 rad(Si)/s, and then exposed to neutron fluence up to 1 × 10{sup 11} n/cm{sup 2} (1-MeV equivalent neutron fluence). One sample was first exposed to neutron fluence up to 1 × 10{sup 11} n/cm{sup 2} (1-MeV equivalent neutron fluence), and then exposed to {sup 60}Co γ-rays up to the TID level of 200 krad(Si) at the dose rate of 0.2 rad(Si)/s. The mean dark signal (K{sub D}), the dark signal non-uniformity (DSNU), and the noise (V{sub N}) versus the total dose and neutron fluence has been investigated. The degradation mechanisms of CMOS APS image sensors have been analyzed, especially for the interaction induced by neutron displacement damage and TID damage.

  5. Combined reactor neutron beam and 60Co γ-ray radiation effects on CMOS APS image sensors

    Directory of Open Access Journals (Sweden)

    Zujun Wang

    2015-02-01

    Full Text Available The combined reactor neutron beam and 60Co γ-ray radiation effects on complementary metal-oxide semiconductor (CMOS active pixel sensors (APS have been discussed and some new experimental phenomena are presented. The samples are manufactured in the standard 0.35-μm CMOS technology. Two samples were first exposed to 60Co γ-rays up to the total ionizing dose (TID level of 200 krad(Si at the dose rates of 50.0 and 0.2 rad(Si/s, and then exposed to neutron fluence up to 1 × 1011 n/cm2 (1-MeV equivalent neutron fluence. One sample was first exposed to neutron fluence up to 1 × 1011 n/cm2 (1-MeV equivalent neutron fluence, and then exposed to 60Co γ-rays up to the TID level of 200 krad(Si at the dose rate of 0.2 rad(Si/s. The mean dark signal (KD, the dark signal non-uniformity (DSNU, and the noise (VN versus the total dose and neutron fluence has been investigated. The degradation mechanisms of CMOS APS image sensors have been analyzed, especially for the interaction induced by neutron displacement damage and TID damage.

  6. Combined reactor neutron beam and 60Co γ-ray radiation effects on CMOS APS image sensors

    International Nuclear Information System (INIS)

    The combined reactor neutron beam and 60Co γ-ray radiation effects on complementary metal-oxide semiconductor (CMOS) active pixel sensors (APS) have been discussed and some new experimental phenomena are presented. The samples are manufactured in the standard 0.35-μm CMOS technology. Two samples were first exposed to 60Co γ-rays up to the total ionizing dose (TID) level of 200 krad(Si) at the dose rates of 50.0 and 0.2 rad(Si)/s, and then exposed to neutron fluence up to 1 × 1011 n/cm2 (1-MeV equivalent neutron fluence). One sample was first exposed to neutron fluence up to 1 × 1011 n/cm2 (1-MeV equivalent neutron fluence), and then exposed to 60Co γ-rays up to the TID level of 200 krad(Si) at the dose rate of 0.2 rad(Si)/s. The mean dark signal (KD), the dark signal non-uniformity (DSNU), and the noise (VN) versus the total dose and neutron fluence has been investigated. The degradation mechanisms of CMOS APS image sensors have been analyzed, especially for the interaction induced by neutron displacement damage and TID damage

  7. AP1000 status overview

    International Nuclear Information System (INIS)

    The AP1000 is a two-loop, 1000 MWe pressurized water reactor (PWR) with passive safety features and extensive plant simplifications to enhance the construction, operation, and maintenance. The AP1000 design is derived directly from the AP600, a two-loop, 600 MWe PWR. The AP600 uses proven technology, which builds on the over 30 years of operating PWR experience. The AP600 design received Final Design Approval from the U.S. NRC in September 1998 and Design Certification in December 1999. The AP600 meets all of the U.S. electric utility requirements including their cost goals. Although the AP600 is the most cost-effective plant ready for deployment, it is still more expensive than the $1000/kw needed to compete in the United States today In order to develop a cost competitive nuclear power plant Westinghouse has completed design studies which demonstrate that it is feasible to increase the power output of the AP600 to at least 1000 MWe, maintaining its current design configuration, use of proven components and licensing basis. In order to achieve these objectives the AP1000 has been designed within the space constraints of the AP600, while retaining the credibility of proven components and substantial safety margins. This paper describes the changes made to up-rate the AP600 and gives an overview of the plant design. It also summarizes the basis for the AP600 testing program and computer codes being sufficient for the AP1000. (authors)

  8. AP1000® PWR reactor physics analysis with VERA-CS and KENO-VI. Part 1. Zero power physics tests

    International Nuclear Information System (INIS)

    Westinghouse has applied the Core Simulator of the Virtual Environment for Reactor Applications, VERA-CS, under development by the Consortium for Advanced Simulation of LWRs (CASL) to the core physics analysis of the AP1000® PWR. The AP1000 PWR features and advanced first core with radial and axial heterogeneities, including enrichment zoning, multiple burnable absorbers, and a combination of light and heavy control banks to enable the MSHIMTM advanced operational strategy. These advanced features make application of VERA-CS to the AP1000 PWR first core especially relevant to qualify VERA performance. A companion paper at this conference describes the power distribution analysis of the AP1000 PWR with VERA-CS and the KENO Monte-Carlo code. This paper describes the results obtained for the startup physics tests simulations of the AP1000 PWR first core (critical boron, rod worth and reactivity coefficients), supporting the excellent numerical agreement reported in the companion paper for the power distribution. (author)

  9. Analysis of Control Rod Worth Features of MC Simulation in AP1000 Reactor%AP1000核反应堆控制棒价值特性的MC模拟

    Institute of Scientific and Technical Information of China (English)

    谢明亮; 于雷; 陈玉清

    2016-01-01

    针对当前AP000堆芯采用的两类控制棒束,基于MCNP5程序建立堆芯仿真计算模型,分析了含不同硼浓度对堆芯kef与硼微分价值的影响,同时对AP1000棒组价值进行模拟计算,对比分析了黑棒与灰棒插入堆芯对kef的影响。结果表明:基于MC N P5程序建立的模型是正确的,硼微分价值(绝对值)随硼浓度增加呈现下降趋势,其值在-9.16~-13.60范围内变化,符合反应性设计要求,有效增殖系数kef随控制棒插入呈现非线性变化,得到了控制棒的价值变化曲线与拟合关系式,为控制棒在反应堆内紧急控制与功率调节提供参考。%In view of current use of two kinds of control rods in AP1000 reactor,the simulation calculation model was set up based on MCNP5 code,kef and differential value of boron with several different boron concentration were analyzed in the reactor,and simulation of group value rods of AP1000 were calculated at the same time,and the contrast analysis of kef effects was accomplished when black and grey rod insert-ed into the core.Results show that:the model based on MCNP5 code is correct,and the differential value of boron (absolute value)present a downward trend with the increase of boron concentration,and its value changed between 9.16 and 13.60,which is conforms to the requirements of reactive design,and the effec-tive multiplication factor kef present nonlinear variation with rod inserted into the core,and it gets the curves of control rod worth and fitting relation,which provides the reference for emergency control and power regulation with control rod in the reactor.

  10. Analysis and Verification of Direct Vessel Injection Line Break event tree for AP1000 reactor with TRACE code

    Energy Technology Data Exchange (ETDEWEB)

    Queral, C.; Montero-Mayorga, J.; Gonzalez-Cadelo, J.

    2013-07-01

    The AP1000 PRA thermal hydraulic simulations were performed with MAAP code, which allows simulating sequences with low computational efforts. On the other hand, the use of best estimate codes allows verifying PRA results as well as obtaining a greater knowledge of the phenomenology of such sequences. The initiating event with the greatest contribution to core damage is Direct Vessel Injection Line Break (DVILB). This paper presents a review of DVILB sequences of AP1000 with TRACE code for verifying sequences previously analyzed by Westinghouse with MAAP code. The sequences which configure the DVILB event tree during short term have been simulated. The results obtained confirm the ones obtained in AP1000 PRA.

  11. TRAC analysis of an 80% pump-side, cold-leg, large-break loss-of-coolant accident for the Westinghouse AP600 advanced reactor design

    International Nuclear Information System (INIS)

    An updated TRAC 80% pump-side, cold-leg, large-break (LB) loss-of-coolant accident (LOCA) has been calculated for the Westinghouse AP600 advanced reactor design. The updated calculation incorporates major code error corrections, model corrections, and plant design changes. The break size and location were calculated by Westinghouse to be the most severe LBLOCA for the AP600 design. The LBLOCA transient was calculated to 280 s, which is the time of in-containment refueling water-storage-tank injection. All fuel rods were quenched completely by 240 s. Peak cladding temperatures (PCTs) were well below the licensing limit of 1,478 K (2,200 F) but were very near the cladding oxidation temperature of 1,200 K (1,700 F). Transient event times and PCTs for the TRAC calculation were in reasonable agreement with those calculated by Westinghouse using their WCOBRA/TRAC code. However, there were significant differences in the detailed phenomena calculated by the two codes, particularly during the blowdown and refill periods. The reasons for these differences are still being investigated

  12. DBD reactor design and optimization in continuous AP-PECVD from HMDSO/N2/N2O mixture

    Science.gov (United States)

    Hotmar, Petr; Caquineau, Hubert; Cozzolino, Raphaël; Gherardi, Nicolas

    2016-02-01

    Dielectric barrier discharge (DBD) deposition of thin films is increasingly studied as a promising alternative to other non-thermal processes such as low-pressure plasma-enhanced chemical vapor deposition (PECVD) or wet-coating. In this paper we demonstrate how optimizing gas injection in the DBD results in an improvement in the reactor performance. We propose to confine the precursor gas close to the deposition substrate by an additional gas flow. The performance of this design is studied though simulation of mass transport. To optimize the deposited thickness, gas cost and reactor clogging, we assess the influence of the confinement, total gas flow rate and DBD length. The confinement is found to reduce reactor clogging, even for long DBD, and increase the deposit thickness. This increase in thickness requires a proportionate increase in the gas flow-rate, making the gas-cost the main limitation of the proposed design. We show, however, that by fine-tuning the operating conditions a beneficial compromise can be obtained between the three optimization objectives.

  13. AP1000. The PWR revisited

    International Nuclear Information System (INIS)

    The distinguishing features of Westinghouse's AP1000 advanced passive pressurized water reactor are highlighted. In particular, the AP1000's passive safety features are described as well as their implications for simplifying the design, construction, and operation of this design compared to currently operating plants, and significantly increasing safety margins over current plants as well. The AP1000 design specifically incorporates the knowledge acquired from the substantial accumulation of power reactor operating experience and benefits from the application of the Probabilistic Risk Assessment in the design process itself. The AP1000 design has been certified by the US Nuclear Regulatory Commission under its new rules for licensing new nuclear plants, 10 CFR Part 52, and is the subject of six combined Construction and Operating License applications now being developed. Currently the AP1000 design is being assessed against the EUR Rev C requirements for new nuclear power plants in Europe. (author)

  14. Pirt/scaling assessment for AP1000

    International Nuclear Information System (INIS)

    The AP1000 is an up-rated version of the AP600 passive plant design that recently received final design certification from the US NRC. Like AP600, the AP1000 is a two-loop, pressurized water reactor featuring passive core cooling and passive containment safety systems. As the AP1000 design is essentially a scaled-up version of the AP600, it is expected that the AP600 Phenomena Identification and Ranking Tables (PIRTs) and much of the AP600 test database should be applicable in applying for design certification for the AP1000. In an effort to confirm this for pursuit of a license, the PIRTs and test facility scaling are re-assessed in view of AP1000. (author)

  15. Westinghouse AP1000 containment design

    International Nuclear Information System (INIS)

    The Westinghouse AP1000 Program is aimed at making available a nuclear power plant that is economical in the U.S deregulated electrical power industry in the near-term. The AP1000 is two-loop 1000 MWe pressurizer water reactor (PWR). It is an up rated version of the AP600. The AP1000 uses passive safety systems to provide significant and measurable improvements in plant simplification, safety, reliability, investment protection and plant costs. The AP1000 uses proven technology, which builds on 50 years of operating PWR experience. The AP1000 received Final Design Approval by the Nuclear Regulatory Commission in September 2004. The AP1000 is provided with a high integrity containment using a substantial steel pressure vessel. The steel surface is used to remove decay heat during design basis accidents. One of the other advantages of the AP1000 containment design over evolutionary PWRs, is improved containment isolation. This has been accomplished by reducing the number of penetrations by ∼50% and improving the isolation valves. As a result, the AP1000 will have fewer difficulties during containment leak testing. The AP1000 containment design meets the Advanced Light Water Reactor Utility Requirements Document (URD) requirements and has been reviewed and approved by the NRC, as was the AP600 containment design. Furthermore, the containment design has also been recognized as meeting the EUR containment requirements by the European utilities. This paper reviews the AP1000 containment vessel design, construction, post accident behavior, and severe accident performance. In addition, the radiation release models, assumptions and both short and long-term performance are also discussed. (authors)

  16. 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)

  17. AP600 design certification thermal hydraulics testing and analysis

    International Nuclear Information System (INIS)

    Westinghouse Electric Corporation, in conjunction with the Department of Energy and the Electric Power Research Institute, have been developing an advanced light water reactor design; the AP600. The AP600 is a 1940 Mwt, 600Mwe unit which is similar to a Westinghouse two-loop Pressurized Water Reactor. The accumulated knowledge on reactor design to reduce the capital costs, construction time, and the operational and maintenance cost of the unit once it begins to generate electrical power. The AP600 design goal is to maintain an overall cost advantage over fossil generated electrical power

  18. AP600 design certification thermal hydraulics testing and analysis

    Energy Technology Data Exchange (ETDEWEB)

    Hochreiter, L.E.; Piplica, E.J.

    1995-09-01

    Westinghouse Electric Corporation, in conjunction with the Department of Energy and the Electric Power Research Institute, have been developing an advanced light water reactor design; the AP600. The AP600 is a 1940 Mwt, 600Mwe unit which is similar to a Westinghouse two-loop Pressurized Water Reactor. The accumulated knowledge on reactor design to reduce the capital costs, construction time, and the operational and maintenance cost of the unit once it begins to generate electrical power. The AP600 design goal is to maintain an overall cost advantage over fossil generated electrical power.

  19. AP600 - an ALWR conceptual design

    International Nuclear Information System (INIS)

    The Electric Power Research Institute is spearheading an effort to develop utility requirements for the Advanced Light Water Reactor (ALWR) plants which will become the next generation nuclear power plants for the U.S. This EPRI ALWR Program involves utilities, the U.S. Department of Energy, the U.S. Nuclear Regulatory Commission, and various industry suppliers. The ALWR Program is aimed at ALWR plants which incorporate step improvements in safety, reliability, operability and power generation costs. As part of the ALWR efforts, a Westinghouse team is conducting conceptual design development of a PWR plant design called the AP600, reflecting advanced passive safety features and the chosen 600 MWe plant output. The AP600 conceptual design provides significant improvements while employing proven component technology. This paper describes the basic reactor and primary coolant system features, the passive safety system features, and plant arrangement/construction features of AP600

  20. AP1000's advanced control room

    International Nuclear Information System (INIS)

    AP1000 is a passive Advanced Light Water Reactor designed by Westinghouse Electric Company to comply with the Electric Power Research Institute's (EPRI) Advanced Light Water Reactor (ALWR) Utility Requirements Document (URD). AP600, the predecessor to AP1000, received Design Certification by the US Nuclear Regulatory Commission (USNRC) in 1999. The AP1000 received its Final Design Approval in the Fall of 2004 and Design Certification is expected in the fall of 2005. During both of these licensing efforts a control room and Human Machine Interface (HMI) design process was submitted and approved. Realizing that Instrumentation and Control (I and C) and HMI technology changes rapidly, Westinghouse chose to delay the detailed design of the control room and operator interfaces. This allows the latest technology to be used when a plant is actually going to be built. That time has now come. This paper describes the preliminary designs of the AP1000 main control room (MCR) and HMI planned for use in new plants both in the United States and abroad. The paper also addresses how the certified design process is being conducted to complete the detailed HMI designs. (authors)

  1. Reactors

    International Nuclear Information System (INIS)

    Purpose: To provide a spray cooling structure wherein the steam phase in a bwr reactor vessel can sufficiently be cooled and the upper cap and flanges in the vessel can be cooled rapidly which kept from direct contaction with cold water. Constitution: An apertured shielding is provided in parallel spaced apart from the inner wall surface at the upper portion of a reactor vessel equipped with a spray nozzle, and the lower end of the shielding and the inner wall of the vessel are closed to each other so as to store the cooling water. Upon spray cooling, cooling water jetting out from the nozzle cools the vapor phase in the vessel and then hits against the shielding. Then the cooling water mostly falls as it is, while partially enters through the apertures to the back of the shielding plate, abuts against stoppers and falls down. The stoppers are formed in an inverted L shape so that the spray water may not in direct contaction with the inner wall of the vessel. (Horiuchi, T.)

  2. 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)

  3. AP statistics crash course

    CERN Document Server

    D'Alessio, Michael

    2012-01-01

    AP Statistics Crash Course - Gets You a Higher Advanced Placement Score in Less Time Crash Course is perfect for the time-crunched student, the last-minute studier, or anyone who wants a refresher on the subject. AP Statistics Crash Course gives you: Targeted, Focused Review - Study Only What You Need to Know Crash Course is based on an in-depth analysis of the AP Statistics course description outline and actual Advanced Placement test questions. It covers only the information tested on the exam, so you can make the most of your valuable study time. Our easy-to-read format covers: exploring da

  4. APS Science 2006.

    Energy Technology Data Exchange (ETDEWEB)

    Gibson, J. M.; Fenner, R. B.; Long, G.; Borland, M.; Decker, G.

    2007-05-24

    In my five years as the Director of the Advanced Photon Source (APS), I have been fortunate to see major growth in the scientific impact from the APS. This year I am particularly enthusiastic about prospects for our longer-term future. Every scientific instrument must remain at the cutting edge to flourish. Our plans for the next generation of APS--an APS upgrade--got seriously in gear this year with strong encouragement from our users and sponsors. The most promising avenue that has emerged is the energy-recovery linac (ERL) (see article on page xx), for which we are beginning serious R&D. The ERL{at}APS would offer revolutionary performance, especially for x-ray imaging and ultrafast science, while not seriously disrupting the existing user base. I am very proud of our accelerator physics and engineering staff, who not only keep the current APS at the forefront, but were able to greatly impress our international Machine Advisory Committee with the quality of their work on the possible upgrade option (see page xx). As we prepare for long-term major upgrades, our plans to develop and optimize all the sectors at APS in the near future are advancing. Several new beamlines saw first light this year, including a dedicated powder diffraction beamline (11-BM), two instruments for inelastic x-ray scattering at sector 30, and the Center for Nanoscale Materials (CNM) Nanoprobe beamline at sector 26. Our partnership in the first x-ray free-electron laser (LCLS) to be built at Stanford contributes to revolutionary growth in ultrafast science (see page xx), and we are developing a pulse chirping scheme to get ps pulses at sector 7 of the APS within a year or so. In this report, you will find selected highlights of scientific research at the APS from calendar year 2006. The highlighted work covers diverse disciplines, from fundamental to applied science. In the article on page xx you can see the direct impact of APS research on technology. Several new products have emerged from

  5. APS Science 2009

    International Nuclear Information System (INIS)

    It is my pleasure to introduce the 2009 annual report of the Advanced Photon Source. This was a very good year for us. We operated with high reliability and availability, despite growing problems with obsolete systems, and our users produced a record output of publications. The number of user experiments increased by 14% from 2008 to more than 3600. We congratulate the recipients of the 2009 Nobel Prize in Chemistry-Venkatraman Ramakrishnan (Cambridge Institute for Medical Research), Thomas Steitz (Yale University), and Ada Yonath (Weizmann Institute) - who did a substantial amount of this work at APS beamlines. Thanks to the efforts of our users and staff, and the ongoing counsel of the APS Scientific Advisory Committee, we made major progress in advancing our planning for the upgrade of the APS (APS-U), producing a proposal that was positively reviewed. We hope to get formal approval in 2010 to begin the upgrade. With advocacy from our users and the support of our sponsor, the Office of Basic Energy Sciences in the Department of Energy (DOE) Office of Science, our operating budgets have grown to the level needed to more adequately staff our beamlines. We were also extremely fortunate to have received $7.9 M in American Recovery and Reinvestment Act ('stimulus') funding to acquire new detectors and improve several of our beamlines. The success of the new Linac Coherent Light Source at Stanford, the world's first x-ray free-electron laser, made us particularly proud since the undulators were designed and built by the APS. Among other highlights, we note that more than one-quarter of the 46 Energy Frontier Research Centers, funded competitively across the U.S. in 2009 by the DOE, included the Advanced Photon Source in their proposed work, which shows that synchrotron radiation, and the APS in particular, are central to energy research. While APS research covers everything from fundamental to applied science (reflected by the highlights in this report), the challenge

  6. APS Science 2009.

    Energy Technology Data Exchange (ETDEWEB)

    Gibson, J. M; Mills, D. M.; Gerig, R.

    2010-05-01

    It is my pleasure to introduce the 2009 annual report of the Advanced Photon Source. This was a very good year for us. We operated with high reliability and availability, despite growing problems with obsolete systems, and our users produced a record output of publications. The number of user experiments increased by 14% from 2008 to more than 3600. We congratulate the recipients of the 2009 Nobel Prize in Chemistry-Venkatraman Ramakrishnan (Cambridge Institute for Medical Research), Thomas Steitz (Yale University), and Ada Yonath (Weizmann Institute) - who did a substantial amount of this work at APS beamlines. Thanks to the efforts of our users and staff, and the ongoing counsel of the APS Scientific Advisory Committee, we made major progress in advancing our planning for the upgrade of the APS (APS-U), producing a proposal that was positively reviewed. We hope to get formal approval in 2010 to begin the upgrade. With advocacy from our users and the support of our sponsor, the Office of Basic Energy Sciences in the Department of Energy (DOE) Office of Science, our operating budgets have grown to the level needed to more adequately staff our beamlines. We were also extremely fortunate to have received $7.9 M in American Recovery and Reinvestment Act ('stimulus') funding to acquire new detectors and improve several of our beamlines. The success of the new Linac Coherent Light Source at Stanford, the world's first x-ray free-electron laser, made us particularly proud since the undulators were designed and built by the APS. Among other highlights, we note that more than one-quarter of the 46 Energy Frontier Research Centers, funded competitively across the U.S. in 2009 by the DOE, included the Advanced Photon Source in their proposed work, which shows that synchrotron radiation, and the APS in particular, are central to energy research. While APS research covers everything from fundamental to applied science (reflected by the highlights in this report

  7. Preliminary study on operational transient analysis for AP1000

    International Nuclear Information System (INIS)

    Typical operational transients have been analyzed with RELAP5 code for AP1000 NPP, in which the reactor power control system was simulated, including Reactor Control System (RECS), Rapid Power Reduction (RPR), Steam Dump Control System (SDCS), Feedwater Control System (FWCS), Pressurizer Pressure Control System (PPCS) and Pressurizer Level Control System (PLCS). It indicates that the plant control system is effective to bring the plant into a safe steady state without actuation of reactor protection system under the representative operational transient, only depends upon the plant control system adjustment. Analysis results show that the design requirement will be met for AP1000 operational transient. (authors)

  8. Application of the SPA in the design of a hydrogen producer plant coupled to a nuclear reactor; Aplicacion del APS en el diseno de una planta productora de hidrogeno acoplada a un reactor nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz S, T.; Nelson, P. F.; Francois, J. L. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac No. 8532, Col. Progreso, 62550 Jiutepec, Morelos (Mexico); Cruz G, M. J., E-mail: truizsmx@yahoo.com.mx [UNAM, Facultad de Quimica, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2013-10-15

    At the present time, one of the processes that is broadly investigated and that, theoretically demonstrates to be one of the most efficient for the hydrogen production, is the thermal-chemistry cycle Sulfur-Iodine (S-I) coupled to a nuclear reactor of very high temperature (VHTR). Because this chemical process of hydrogen production requires of a great inventory of toxic materials (sulphide compounds, hydriodic acid and iodine), is necessary the design of emergency systems with the purpose of protecting the facilities and the equipment s, the environment, as well as the near population. Given the impact of an accidental liberation of the process materials, as well as the proximity with the nuclear plant, is necessary that these emergency systems are the most reliable possible. This way, the results of the consequences analysis are utilized for the optimal localization of the gas sensors that activate the emergency systems, and the flows of the substances that are used for the leakage control. For all this, the use of the Safety Probabilistic Analysis methodology, as well as some standards of the nuclear industry, can be applied to the chemical installation to determine the fault sequences that can take to final states of not controlled leakage. This way, the use of methodologies of Event Tree Analysis and Fault Trees show in their results the components that but contribute in fault of such systems. In this work, is presented the evaluation of the joined models of event and fault trees and like with the obtained results, some proposals to increase the safety of the facilities are exposed. Also, the results of the evaluations of these proposals, and their impact of the probability of the not controlled fault sequences in a plant that is still in design stage are showed. (Author)

  9. Testing of the AP600 automatic depressurization system

    International Nuclear Information System (INIS)

    The Automatic Depressurization System (ADS) of the Westinghouse AP600 reactor will be used to provide controlled depressurization of the reactor coolant system (RCS). This will, in turn allow the initiation and long term operation of gravity driven cooling flow in the RCS. ADS tests were conducted at the VAPORE test facility in Casaccia, Italy through a Technical Cooperation Agreement between Westinghouse, ENEA, SOPREN/ANSALDO, and ENEL to produce data for the development and verification of computer codes to simulate the system. The test program also provided insights about the operation of valves supplied from various vendors that could be used in the AP600 ADS. The data gathered from the tests showed the ability of the ADS design to fulfill its function over the range of conditions expected in the AP600. The tests also demonstrated the abilities of gate and globe valves from several vendors to initiate and terminate an ADS blowdown as could be required in the AP600

  10. AP1000 radiation monitoring system design and engineering solution

    International Nuclear Information System (INIS)

    It presents the design concept and solution, including system integration architecture, communication network design and monitoring software of Radiation Monitoring System in Sanmen and Haiyang AP1000 nuclear power plant. The design of AP1000 radiation monitoring system has been simplified comparing to general Pressurized Water Reactor. Radiation monitoring network is composed of the radiation monitoring computer system (CRPS-1000) and four kinds of radiation monitors through standard interface. The data of radiation monitoring system are monitored and managed by CRPS-1000. (authors)

  11. APS Science 2007.

    Energy Technology Data Exchange (ETDEWEB)

    2008-05-30

    This report provides research highlights from the Advanced Photon Source (APS). Although these highlights represent less than 10% of the published work from the APS in 2007, they give a flavor of the diversity and impact of user research at the facility. In the strategic planning the aim is to foster the growth of existing user communities and foresee new areas of research. This coming year finds the APS engaged in putting together, along with the users, a blueprint for the next five years, and making the case for a set of prioritized investments in beamlines, the accelerator, and infrastructure, each of which will be transformational in terms of scientific impact. As this is written plans are being formulated for an important user workshop on October 20-21, 2008, to prioritize strategic plans. The fruit from past investments can be seen in this report. Examples include the creation of a dedicated beamline for x-ray photon correlation spectroscopy at Sector 8, the evolution of dedicated high-energy x-ray scattering beamlines at sectors 1 and 11, a dedicated imaging beamline at Sector 32, and new beamlines for inelastic scattering and powder diffraction. A single-pulse facility has been built in collaboration with Sector 14 (BioCARS) and Phil Anfinrud at the National Institutes of Health, which will offer exceptionally high flux for single-pulse diffraction. The nanoprobe at Sector 26, built and operated jointly by the Argonne Center for Nanoscale Materials and the X-ray Operations and Research (XOR) section of the APS X-ray Science Division, has come on line to define the state of the art in nanoscience.

  12. APS Science 2007

    International Nuclear Information System (INIS)

    This report provides research highlights from the Advanced Photon Source (APS). Although these highlights represent less than 10% of the published work from the APS in 2007, they give a flavor of the diversity and impact of user research at the facility. In the strategic planning the aim is to foster the growth of existing user communities and foresee new areas of research. This coming year finds the APS engaged in putting together, along with the users, a blueprint for the next five years, and making the case for a set of prioritized investments in beamlines, the accelerator, and infrastructure, each of which will be transformational in terms of scientific impact. As this is written plans are being formulated for an important user workshop on October 20-21, 2008, to prioritize strategic plans. The fruit from past investments can be seen in this report. Examples include the creation of a dedicated beamline for x-ray photon correlation spectroscopy at Sector 8, the evolution of dedicated high-energy x-ray scattering beamlines at sectors 1 and 11, a dedicated imaging beamline at Sector 32, and new beamlines for inelastic scattering and powder diffraction. A single-pulse facility has been built in collaboration with Sector 14 (BioCARS) and Phil Anfinrud at the National Institutes of Health, which will offer exceptionally high flux for single-pulse diffraction. The nanoprobe at Sector 26, built and operated jointly by the Argonne Center for Nanoscale Materials and the X-ray Operations and Research (XOR) section of the APS X-ray Science Division, has come on line to define the state of the art in nanoscience

  13. Learning about Antiphospholipid Syndrome (APS)

    Science.gov (United States)

    ... and links from the National Institutes of Health. Learning About Antiphospholipid Syndrome (APS) What is antiphospholipid syndrome ( ... with APS include : Systemic Vascular Thrombosis While the deep veins of the legs are the most frequent ...

  14. AP1000 passive safety system design and analysis

    International Nuclear Information System (INIS)

    Westinghouse Electric Company has designed an advanced 600 MW nuclear power plant called the AP600. The AP600 uses passive safety systems to enhance plant safety and to satisfy US licensing requirements. The use of passive safety systems has provided significant and measurable improvements in plant simplification, safety, reliability, investment protection and plant costs. The overnight capital cost for the first AP600 plant is calculated to be between 1300- 1500 $/kw depending on the site selection. Although the AP600 is the most cost effective plant ready for deployment, it is still more expensive than the $1000/kw needed to compete in the United States today. In order to develop a cost competitive nuclear power plant Westinghouse has completed design studies which demonstrate that it is feasible to increase the power output of the AP600 to at least 1000 MW, maintaining its current design configuration, use of proven components and licensing basis. The AP1000 reactor and passive safety features retain the same configuration as the AP600. The approach to designing the passive core cooling features is to evaluate each feature to determine if changes are necessary to provide proper safety margins at the higher power rating. Both design basis and PRA based accidents sequences are considered in this evaluation. Insights from the extensive AP600 test and analysis program are used to assist in this process. The results of preliminary accident analysis for DBA and PRA sequences are used to demonstrate the effectiveness of this approach. (author)

  15. AP600 containment purge radiological analysis

    Energy Technology Data Exchange (ETDEWEB)

    O`Connor, M.; Schulz, J.; Tan, C. [Bechtel Power Corporation (United States)] [and others

    1995-02-01

    The AP600 Project is a passive pressurized water reactor power plant which is part of the Design Certification and First-of-a-Kind Engineering effort under the Advanced Light Water Reactor program. Included in this process is the design of the containment air filtration system which will be the subject of this paper. We will compare the practice used by previous plants with the AP600 approach to meet the goals of industry standards in sizing the containment air filtration system. The radiological aspects of design are of primary significance and will be the focus of this paper. The AP600 Project optimized the design to combine the functions of the high volumetric flow rate, low volumetric flow rate, and containment cleanup and other filtration systems into one multi-functional system. This achieves a more simplified, standardized, and lower cost design. Studies were performed to determine the possible concentrations of radioactive material in the containment atmosphere and the effectiveness of the purge system to keep concentrations within 10CFR20 limits and within offsite dose objectives. The concentrations were determined for various reactor coolant system leakage rates and containment purge modes of operation. The resultant concentrations were used to determine the containment accessibility during various stages of normal plant operation including refueling. The results of the parametric studies indicate that a dual train purge system with a capacity of 4,000 cfm per train is more than adequate to control the airborne radioactivity levels inside containment during normal plant operation and refueling, and satisfies the goals of ANSI/ANS-56.6-1986 and limits the amount of radioactive material released to the environment per ANSI/ANS 59.2-1985 to provide a safe environment for plant personnel and offsite residents.

  16. AP1000R licensing and deployment in the United States

    International Nuclear Information System (INIS)

    In recent years, both domestic and foreign utilities have turned to the standardized Westinghouse AP1000 plant design in satisfying their near - and long-term - sustainable energy needs. As direct support to these actions, licensing the AP1000 design has played a significant role by providing one of the fundamental bases in clearing regulatory hurdles leading to the start of new plant construction. Within the U.S. alone, Westinghouse AP1000 licensing activities have reached unprecedented milestones with the approvals of both AP1000 Design Certification and Southern Company's combined construction permit and operating license (COL) application directly supporting the construction of two new nuclear plants in Georgia. Further COL application approvals are immediately pending for an additional two AP1000 plants in South Carolina. And, across the U.S. nuclear industry spectrum, there are 10 other COL applications under regulatory review representing some 16 new plants at 10 sites. In total, these actions represent the first wave of new plant licensing under the regulatory approval process since 1978. Fundamental to the Nuclear Regulatory Commission's AP1000 Design Certification is the formal recognition of the AP1000 passive safety design through regulatory acceptance rulemaking. Through recognition and deployment of the AP1000 Design Certification, the utility licensee / operator of this reactor design are now offered an opportunity to use a simplified 'one-step' combined license process, thereby managing substantial back-end construction schedule risk from regulatory and intervention delays. Application of this regulatory philosophy represents both acceptance and encouragement of standardized reactor designs like the AP1000. With the recent AP1000 Design Certification and utility COL acceptances, the fundamental licensing processes of this philosophy have successfully proven the attainment of significant milestones with the next stage licensing actions directed

  17. CGM ApS Årsberetning til DANAK

    DEFF Research Database (Denmark)

    De Chiffre, Leonardo

    Denne årsberetning omfatter CGM ApS' akkrediterede virksomhed i kalenderåret 2003. Årsberetningen er udarbejdet til DANAK (Dansk Akkreditering, ErhvervsfremmeStyrelsen), som led i opfyldelsen af laboratoriets informationspligt i henhold til gældende regler.......Denne årsberetning omfatter CGM ApS' akkrediterede virksomhed i kalenderåret 2003. Årsberetningen er udarbejdet til DANAK (Dansk Akkreditering, ErhvervsfremmeStyrelsen), som led i opfyldelsen af laboratoriets informationspligt i henhold til gældende regler....

  18. AP1000 design adaptation to European Markets and EUR compliance

    International Nuclear Information System (INIS)

    The AP1000 plant is an 1100-MWe pressurized water reactor (PWR) with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance and safety. One of the key approaches in the AP1000 design is to use passive features to mitigate design basis accidents. In addition to redundancy, these features incorporate diversity based on PRA insights. The AP1000 design has incorporated a standardization approach, which together with the level of safety achieved by the passive safety features, results in a plant design that can be applied to different geographical regions with varying regulatory standards and utility expectations without major changes. Westinghouse has cooperated for almost 2 decades with European utilities to ensure adaptation of the AP1000 design to European market. The AP1000 50 Hz standard design (also referred to as European Passive Standard) is the resulting adaptation of the AP1000 design to European market needs and requirements, addressing both customer input from the EPP program and regulatory needs identified in the UK GDA process. This standard 50 Hz design retains the overall AP1000 design (safe, simple, standard), the use of proven components and its cost, safety and operability advantages, while it incorporates some changes to adapt to the European environment. In this paper, the key changes incorporated into the AP1000 50 Hz design are discussed, including: -) Adaptation of the electrical systems and Turbine adaptation from 60 Hz to 50 Hz, including approach to IEC vs IEEE compliance; -) Modifications to defense in depth (US class D, European Class 2) and other systems to simplify European licensing and address customer requirements; -) Option for adoption of KSB RUV type Main Reactor Coolant Pumps; -) Limited design adaptations in the areas of instrumentation-control and ventilation and filtration to adapt to European requirements and simplify the licensing process

  19. AP physics B crash course

    CERN Document Server

    Howell, Rebecca

    2012-01-01

    AP Physics B Crash Course - Get a Higher Advanced Placement Score in Less Time Crash Course is perfect for the time-crunched student, the last-minute studier, or anyone who wants a refresher on the subject. Our AP Physics B Crash Course gives you: Targeted, Focused Review - Study Only What You Need to Know The Crash Course is based on an in-depth analysis of the AP Physics B course description outline and actual AP test questions. It covers only the information tested on the exam, so you can make the most of your valuable study time. Our easy-to-read format covers: mechanics, kinetic theory, t

  20. 76 FR 73720 - Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Westinghouse AP1000...

    Science.gov (United States)

    2011-11-29

    ... COMMISSION Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Westinghouse AP1000 Pressurized..., NUREG-2103, Revision 0, ``Knowledge and Abilities Catalog for Nuclear Power Plant Operators... with the Operator Licensing Examination Standards for Power Reactors (NUREG-1021) will sample...

  1. Center for Geometrisk Metrologi, CGM ApS

    DEFF Research Database (Denmark)

    De Chiffre, Leonardo

    Denne årsberetning omfatter CGM ApS' akkrediterede virksomhed i kalenderåret 2002. Årsberetningen er udarbejdet til DANAK (Dansk Akkreditering, Erhvervsfremme Styrelsen), som led i opfyldelsen af laboratoriets informationspligt i henhold til gældende regler (Teknisk Forskrift Nr. TF4 af 2000...

  2. Perfection of power release in WWER reactor core

    International Nuclear Information System (INIS)

    Axial processes (AP) during reactor transition regime were studied. An algorithm for supporting a stationary AP value was developed. It was realised at Khmelnitsky NPP, is connected with boron regulation and satisfies all regulatory requirements

  3. AP-42 REVISION: COKE OVENS

    Science.gov (United States)

    The document "Compilation of Air Pollutant Emission Factors" (AP-42) has been published by the U. S. Environmental Protection Agency (EPA) since 1972. Supplements to AP-42 have been routinely published to add new emission source categories and to update existing emission factor...

  4. Learning through delivery, Westinghouse AP1000 plant construction

    International Nuclear Information System (INIS)

    The AP1000 plant, which is a 1100 MWe class pressurized water reactor with passive safety features, is designed around a conventional 2 loop, 2 steam generator primary system configuration with 2 hot legs, 4 reactor coolant pumps directly mounted in the steam generator lower head and 4 cold legs. A particular feature of AP1000 is its modular construction to minimize the time and cost of construction. Modular construction allows activities to be run in parallel, it allows more activities to be performed in a controlled factory instead of in the field, and it provides a better level of quality. The AP1000 plant design includes 106 structural modules and 52 mechanical modules. Structural modules include all penetrations for piping, cable trays, HVAC duct runs, and all reinforcement for pipe, equipment hangers, and supports. Structural modules are shipped in sub-modules to support transportation by rail or truck or barge. Mechanical modules contain equipment such as pumps, tanks, heat exchangers, air-handling units, and filters along with interconnecting pipes, valves, instruments, wiring and support services. Modular construction requires strong coordination between engineering, supply chain and construction. A total of 8 AP1000 units are currently under construction in China and in the United States. The lessons learned and best practices of each new AP1000 construction are systematically incorporated into the standard design. (A.C.)

  5. AP600 Shield building

    International Nuclear Information System (INIS)

    In order to minimize capital costs and save time in the global construction time schedule for the AP600 Nuclear Power Plant, planned in 36 months from excavation up to the fuel charging, ANSALDO has developed an innovative Shield Building Conical Roof design having the following basic characteristics: i) can be erected approximately in less than two months; ii) allows the functionality of the Passive Containment Cooling System (PCSS) located in the PCCS tank and in the Valve Room anchored directly to the conical roof itself; iii) satisfies the structural loads design as Safe Shutdown Earthquake, or the Aircraft Crash and both integrated with the sloshing analysis for the tank located at the top of the conical roof. The most important aspects of this new roof are: a) use of prefabricated precast panels; b) address the erection of the formworks using temporary structures having the capability of becoming final elements; c) develop a modular rebars sizing and design in order to perform the most important portion of the job in the workshop; d) second pouring construction sequence assuring full integration with the formwork function; e) modular construction of the PCSS tank at the top of the conical roof. An interesting evaluation has been also performed in calculating sloshing phenomenon in the PCSS tank by comparing detailed 3D Finite Element Model approach and simplified qualified formulas dedicated to this phenomenon. (author). 2 figs

  6. Final report for tank 241-AP-101, grab samples 1AP-95-1, 1AP-95-2, 1AP-95-3, 1AP-95-4, 1AP-95-5, and 1AP-95-6

    International Nuclear Information System (INIS)

    Six supernate grab samples (1AP-95-1 through 6) and one field blank (1AP-95-7) were taken from tank 241-AP-101, on Nov. 10 and 13, 1995. Analyses were performed in support of the Safety Screening and the Waste Compatibility Safety programs. All analytical results were within the action limits stated in the TSAP

  7. Final report for tank 241-AP-101, grab samples 1AP-95-1, 1AP-95-2, 1AP-95-3, 1AP-95-4, 1AP-95-5, and 1AP-95-6

    Energy Technology Data Exchange (ETDEWEB)

    Esch, R.A.

    1996-03-04

    Six supernate grab samples (1AP-95-1 through 6) and one field blank (1AP-95-7) were taken from tank 241-AP-101, on Nov. 10 and 13, 1995. Analyses were performed in support of the Safety Screening and the Waste Compatibility Safety programs. All analytical results were within the action limits stated in the TSAP.

  8. Limits of coolability in the AP1000-related ULPU-2400 configuration V facility

    International Nuclear Information System (INIS)

    The natural circulation flow along a reactor pressure vessel, and associated coolability (nucleate boiling) limits around a heated lower head portion, are considered. The experimental simulations are effectively at full scale. The exit geometry accounts for AP1000-specific features (at the nozzle gallery level), and the optimal shaping of the reflecting thermal insulation is addressed. The results enhance the coolability envelope derived previously, also in ULPU, for the AP600, and suggest that the In-Vessel Retention idea is extendable to higher power reactors such as the AP1000

  9. Westinghouse AP 1000 program status

    International Nuclear Information System (INIS)

    The project 1000 is presented and features are discussed in the paper. Design maturity is characterized by 1300 man-year / $400 million design and testing effort, more than 12 000 design documents completed; 3D computer model developed. It includes structures, equipment, small / large pipe, cable trays, ducts etc. Licensing Maturity is determined by a very thorough and complete NRC review of AP600; 110 man-year effort (NRC) over 6 years, $30 million; independent, confirmatory plant analysis; independent, confirmatory plant testing (ROSA, OSU); over 7400 questions answered, no open items; over 380 meeting with NRC, 43 meetings with ACRS. NRC Design Certification is issued in December 1999. Reasons for developing AP 1000 and design changes are presented. Economic analysis shows an expectation for payback within 20 years. AP1000 provides 75% power uprate for 15% increment in capital cost. AP1000 meets new plant economic targets in the near term

  10. Meet the APS Journal Editors

    Science.gov (United States)

    2016-05-01

    The Editors of the APS journals invite you to join them for conversation. The Editors will be available to answer questions, hear your ideas, and discuss any comments about the journals. All are welcome. Light refreshments will be served.

  11. AP1000 construction schedule

    International Nuclear Information System (INIS)

    Westinghouse performed this study as part of EPRI interest in advancing the use of computer aided processes to reduce the cost of nuclear power plants. EPRI believed that if one could relate appropriate portions of an advanced light water reactor plant model to activities in its construction sequence, and this relationship could be portrayed visually, then optimization of the construction sequence could be developed as never before. By seeing a 3-D representation of the plant at any point in its construction sequence, more informed decisions can be made on the feasibility or attractiveness of follow on or parallel steps in the sequence. The 3-D representation of construction as a function of time (4-D) could also increase the confidence of potential investors concerning the viability of the schedule and the plant ultimate cost. This study performed by Westinghouse confirmed that it is useful to be able to visualize a plant construction in 3-D as a function of time in order to optimize the sequence of construction activities. (author)

  12. Vibration analysis of primary air pump JE01 AP003

    International Nuclear Information System (INIS)

    JE01 AP003 primary coolant pump is one of the main components in the safe operation of the reactor so that needs to be done early detection of damage types and levels of its constituent components. The main components of the pump that is often damaged bearing. The purpose of this paper is to know the symptoms of bearing damage and the level of damage based on vibration analysis. One indication of the bearing has been damaged, that is the vibration or temperature rise in the bearing. One way to detect early symptoms of damage to the pump is to use the vibration response peak Based on the analysis of the measurement results cited the obtained results that the primary coolant pump JE01 AP003 has been damage to a free end looseness bearing with moderate levels of damage. Need JE01 AP003 bearing replacement even though the damage is not severe. (author)

  13. Installation Technology of AP1000 Steam Generator%AP1000蒸汽发生器安装技术

    Institute of Scientific and Technical Information of China (English)

    郑东宏; 王志强; 张明; 门昌华; 胡德全

    2013-01-01

    AP1000 nuclear power plant is a 3rd generation advanced passive 1000 MWe pressurized water reactor plant with two loops of reactor coolant systems .Compared with the conventional 2nd generation pressurized water reactor technology ,the steam generator ( SG) of AP1000 has many improved changes concerning SG property features and arrangement requirements for facilities within the nuclear island . Based on these improved changes and relevant installation practices ,the installation technology of AP 1000 SG has been introduced and analyzed including installation preparation ,transportation ,lifting,and instal-lation construction ,etc., with a view to provide a technical reference to the installation of main equip-ments in steam supply system of nuclear power plant .%AP1000是二环路的1000 MWe级压水堆三代核电厂,采用非能动安全设施,与传统的二代压水堆核电技术相比,蒸汽发生器本体特征和核岛内的就位要求均有较大的改进。根据AP1000蒸汽发生器自身的特点,并在实践的基础上,对蒸汽发生器的现场安装技术,包括安装准备、现场运输、吊装、核岛安装等进行了介绍和分析,为核电站核蒸汽供应系统主设备的现场运输、吊装和安装提供技术参考。

  14. AP-1000 passive in-vessel retention design for a severe accident

    International Nuclear Information System (INIS)

    The AP-1000 is a Westinghouse two-loop 1100 MWe advanced pressurized water reactor (PWR) that uses passive safety features to enhance plant safety and to provide significant and measurable improvements in plant simplification, reliability, investment protection and plant costs. One of the passive safety features of the AP-1000 is In-Vessel Retention. In-Vessel Retention passively provides sufficient external cooling of the reactor vessel to retain a molten core inside the vessel in the unlikely event of a severe accident. This concept was proven by a series of tests and analyses, and offers numerous advantages over other severe accident core management designs. The testing that proved the In-Vessel Retention Concept for AP-1000 also identified a series of features and functions for the reactor vessel insulation, making it different from the reactor vessel insulation in any other nuclear power plant. This paper presents the key functional and interface requirements for the AP-1000 reactor vessel insulation and the design configuration that meets those requirements. Requirements are identified for both normal and severe accident conditions. The requirements for normal conditions are similar to those for any other reactor vessel insulation. The severe accident requirements include features that passively allow containment flood water in the reactor cavity to freely flow between the insulation and reactor vessel and other features that passively allow the resulting steam to freely vent. The AP-1000 reactor vessel insulation must also provide the appropriate annulus to optimally cool the reactor vessel and be structurally adequate to withstand the loads that occur during the severe accident and during certain pipe breaks in containment. (authors)

  15. APS Education and Diversity Efforts

    Science.gov (United States)

    Prestridge, Katherine; Hodapp, Theodore

    2015-11-01

    American Physical Society (APS) has a wide range of education and diversity programs and activities, including programs that improve physics education, increase diversity, provide outreach to the public, and impact public policy. We present the latest programs spearheaded by the Committee on the Status of Women in Physics (CSWP), with highlights from other diversity and education efforts. The CSWP is working to increase the fraction of women in physics, understand and implement solutions for gender-specific issues, enhance professional development opportunities for women in physics, and remedy issues that impact gender inequality in physics. The Conferences for Undergraduate Women in Physics, Professional Skills Development Workshops, and our new Professional Skills program for students and postdocs are all working towards meeting these goals. The CSWP also has site visit and conversation visit programs, where department chairs request that the APS assess the climate for women in their departments or facilitate climate discussions. APS also has two significant programs to increase participation by underrepresented minorities (URM). The newest program, the APS National Mentoring Community, is working to provide mentoring to URM undergraduates, and the APS Bridge Program is an established effort that is dramatically increasing the number of URM PhDs in physics.

  16. BEACONTM Core Monitoring and Analysis for Operations of the Westinghouse AP1000

    International Nuclear Information System (INIS)

    The Westinghouse AP1000 is a highly advanced Generation 3 pressurized water reactor (PWR). The reactor control strategy is considerably different from today's Westinghouse PWRs. AP1000 reactor control utilizes mechanical shim (MShim) for reactivity control of load changes and core depletion in conjunction with boron reactivity shim. The system is designed for several days of power operation without changing the reactor coolant system boron concentration. This along with an advanced reactor coolant pump design allows for a chemistry and volume control system that is much simplified from present PWRs. Furthermore, the nuclear renaissance provides the opportunity for the application of innovative technology in the establishment of behaviors in the operation of the reactor instead of modifying already learned and established practices. The presentation of reactor peaking factor limits, limit monitoring, nuclear data and reactor operations predictive capabilities to the control room will reflect the advanced core, new operating strategy and the opportunity of the AP1000. The proven BEACONTM core monitoring and analysis system will be used in the AP1000. BEACON is presently implemented in over 60 PWRs of different vendor origin on five continents. It is licensed by the regulatory agencies of several countries to provide surveillance of core thermal margins. In addition it provides accurate reactor operations predictions for evolutions like start-up and load changes. The AP1000 implementation of BEACON will build on this extensive experience. From vanadium fixed in-core detector signals and other online plant data, BEACON will continuously update a core model implemented with an advanced 3D nodal code. From this core model, BEACON will measure reactor power distribution, reactivity and shutdown margin and provide information to control room display and alarm presentation systems on margin to thermal and shutdown reactivity limits. Specifically, BEACON will provide

  17. AP1000 - the new standard for nuclear power

    International Nuclear Information System (INIS)

    Full text of publication follows: The AP1000 is the only Generation III+ reactor to receive Final Design Approval (FDA) from the Nuclear Regulatory Commission, and is expected to receive its Design Certification by the end of the year. Building on the proven features of current generation nuclear plants, the AP1000 combines experience with innovation into a design that surpasses current standards of safety and reliability. Use of passive safety features results in a simpler and more compact design that enhances safety, simplifies O and M requirements, and reduces capital and operating costs. At 1117 Mwe, the AP1000 is well suited for almost any grid system and will be fully competitive with combined-cycle gas and comparable fossil fuel plants. The AP1000 is ready to help launch a renaissance in new nuclear plant construction throughout the world. Maturity of Design: In excess of 1300 man-years and $400 million in development funding have been expended on the AP1000. It has undergone extensive, part scale testing at the system, sub-system and component level, in addition to a series of part scale integrated tests. The AP1000 is the most analyzed of the next generation reactors. Simplicity of Design/Economics: The AP1000 uses simplified and innovative passive safety systems to an unprecedented extent. Simplified passive safety systems provide reliable operation, reduced capital costs, and enhanced plant safety with large plant operating margins. The AP1000 features improved reliability through simplicity rather than addition of redundant safety trains. This simpler design is easier and less costly to operate and maintain than larger, more complex plants, while less equipment and smaller buildings translate into lower capital costs and shorter construction durations. After construction, economic benefit will be found in reduced operating and maintenance costs, largely due to reduced operating and maintenance staffing requirements. Construction aspects

  18. AP1000 Features Prevent Potential Containment Recirculation Screen Plugging

    International Nuclear Information System (INIS)

    This paper presents the results of plant design development and evaluations that demonstrate that the AP1000 plant is not subject to potential containment recirculation screen plugging following a loss-of-coolant-accident (LOCA). Following a LOCA in a pressurized water reactor, it is necessary to recirculate water from the containment back into the reactor to maintain long term core cooling. The AP1000 utilizes passive safety systems to provide containment recirculation for long term core cooling following a LOCA. The AP1000 also has non-safety pumps which provide a backup means of providing recirculation. Screens are provided around the recirculation pipes to prevent debris from blocking recirculation flow and core cooling passages. Debris may be generated by the LOCA blowdown from insulation and coatings used inside containment. Even with effective cleanliness programs, there may be some resident debris such as dust and dirt. The potential for plugging the recirculation screens is a current PWR licensing issue. The AP1000 design provides inherent advantages with respect to the potential plugging of containment recirculation screens. These characteristics include prevention of fibrous debris generation, improved debris settling and improved recirculation screen design. Debris settling analysis demonstrates that failure of coatings does not result in debris being transported to the screens before it settles to the floor. Additional analysis also shows that the plant can tolerate conservative amounts of resident debris being transported to the screens. The AP1000 significantly reduces the probability of plugging the containment recirculation screens and significantly reduces inspection and maintenance of coatings used inside containment. (authors)

  19. AP Geography, Environmental Science Thrive

    Science.gov (United States)

    Robelen, Erik W.

    2012-01-01

    Geography may not be particularly known as a hot topic among today's students--even some advocates suggest it suffers from an image problem--but by at least one measure, the subject is starting to come into its own. Across more than 30 topics covered in the Advanced Placement (AP) program, participation in geography is rising faster than any…

  20. Radiation effects on active pixel sensors (APS)

    International Nuclear Information System (INIS)

    Active pixel sensor (APS) is a new generation of image sensors which presents several advantages relatively to charge coupled devices (CCDs) particularly for space applications (APS requires only 1 voltage to operate which reduces considerably current consumption). Irradiation was performed using 60Co gamma radiation at room temperature and at a dose rate of 150 Gy(Si)/h. 2 types of APS have been tested: photodiode-APS and photoMOS-APS. The results show that photoMOS-APS is more sensitive to radiation effects than photodiode-APS. Important parameters of image sensors like dark currents increase sharply with dose levels. Nevertheless photodiode-APS sensitivity is one hundred time lower than photoMOS-APS sensitivity

  1. APS beamline standard components handbook

    International Nuclear Information System (INIS)

    It is clear that most Advanced Photon Source (APS) Collaborative Access Team (CAT) members would like to concentrate on designing specialized equipment related to their scientific programs rather than on routine or standard beamline components. Thus, an effort is in progress at the APS to identify standard and modular components of APS beamlines. Identifying standard components is a nontrivial task because these components should support diverse beamline objectives. To assist with this effort, the APS has obtained advice and help from a Beamline Standardization and Modularization Committee consisting of experts in beamline design, construction, and operation. The staff of the Experimental Facilities Division identified various components thought to be standard items for beamlines, regardless of the specific scientific objective of a particular beamline. A generic beamline layout formed the basis for this identification. This layout is based on a double-crystal monochromator as the first optical element, with the possibility of other elements to follow. Pre-engineering designs were then made of the identified standard components. The Beamline Standardization and Modularization Committee has reviewed these designs and provided very useful input regarding the specifications of these components. We realize that there will be other configurations that may require special or modified components. This Handbook in its current version (1.1) contains descriptions, specifications, and pre-engineering design drawings of these standard components. In the future, the APS plans to add engineering drawings of identified standard beamline components. Use of standard components should result in major cost reductions for CATs in the areas of beamline design and construction

  2. The AP-2 family of transcription factors

    OpenAIRE

    Eckert, Dawid; Buhl, Sandra; Weber, Susanne; Jäger, Richard; Schorle, Hubert

    2005-01-01

    The AP-2 family of transcription factors consists of five different proteins in humans and mice: AP-2α, AP-2β, AP-2γ, AP-2δ and AP-2ε. Frogs and fish have known orthologs of some but not all of these proteins, and homologs of the family are also found in protochordates, insects and nematodes. The proteins have a characteristic helix-span-helix motif at the carboxyl terminus, which, together with a central basic region, mediates dimerization and DNA binding. The amino terminus contains the tra...

  3. Simulation of the Westinghouse AP1000 Response to SBLOCA Using RELAP/SCDAPSIM

    Directory of Open Access Journals (Sweden)

    Ayah Elshahat

    2014-01-01

    Full Text Available Great interest is given now to advanced nuclear reactors especially those using passive safety components. The Westinghouse AP1000 Advanced Passive pressurized water reactor (PWR is an 1117 MWe PWR designed to achieve a high safety and performance record. The AP1000 safety system uses natural driving forces, such as pressurized gas, gravity flow, natural circulation flow, and convection. In this paper, the safety performance of the AP1000 during a small break loss of coolant accident (SBLOCA is investigated. This was done by modelling the AP1000 and the passive safety systems employed using RELAP/SCDAPSIM code. RELAP/SCDAPSIM is designed to describe the overall reactor coolant system (RCS thermal hydraulic response and core behaviour under normal operating conditions or under design basis or severe accident conditions. Passive safety components in the AP1000 showed a clear improvement in accident mitigation. It was found that RELAP/SCDAPSIM is capable of modelling a LOCA in an AP1000 and it enables the investigation of each safety system component response separately during the accident. The model is also capable of simulating natural circulation and other relevant phenomena. The results of the model were compared to that of the NOTRUMP code and found to be in a good agreement.

  4. Doppler Imaging of Ap Stars

    OpenAIRE

    Kuschnig, R.

    1998-01-01

    Doppler imaging, a technique which inverts spectral line profile variations of an Ap star into a two-dimensional abundance maps, provides new observational constraints on diffusion mechanism in the presence of a global magnetic field. A programme is presented here with the aim to obtain abundance distributions of at least five elements on each star, in order to study how different diffusion processes act under influence of a stellar magnetic field. The importance of this multi-element approac...

  5. The APS control system network

    International Nuclear Information System (INIS)

    The APS accelerator control system is a distributed system consisting of operator interfaces, a network, and computer-controlled interfaces to hardware. This implementation of a control system has come to be called the open-quotes Standard Model.close quotes The operator interface is a UNDC-based workstation with an X-windows graphical user interface. The workstation may be located at any point on the facility network and maintain full functionality. The function of the network is to provide a generalized communication path between the host computers, operator workstations, input/output crates, and other hardware that comprise the control system. The crate or input/output controller (IOC) provides direct control and input/output interfaces for each accelerator subsystem. The network is an integral part of all modem control systems and network performance will determine many characteristics of a control system. This paper will describe the overall APS network and examine the APS control system network in detail. Metrics are provided on the performance of the system under various conditions

  6. Preparing Students for the AP Psychology Exam

    Science.gov (United States)

    Whitlock, Kristin

    2013-01-01

    The Advanced Placement Psychology exam is one of the fastest growing exams offered by the College Board. The average percent of change in the number of students taking this exam over the past five years is 12.4%. With 238,962 students taking the exam in 2013, the AP Psychology exam is the sixth largest exam, surpassing AP Biology and AP World…

  7. An AP Calculus Classroom Amusement Park

    Science.gov (United States)

    Ferguson, Sarah

    2016-01-01

    Throughout the school year, AP Calculus teachers strive to teach course content comprehensively and swiftly in an effort to finish all required material before the AP Calculus exam. As early May approaches and the AP Calculus test looms, students and teachers nervously complete lessons, assignments, and assessments to ensure student preparation.…

  8. Westinghouse AP1000® PWR: Meeting Customer Commitments and Market Needs

    International Nuclear Information System (INIS)

    Westinghouse Electric Company once again sets a new industry standard with the AP1000 reactor. Historically, Westinghouse plant designs and technology have forged the cutting edge of worldwide nuclear technology. Today, about 50 percent of the world's 440 nuclear plants are based on Westinghouse technology. The AP1000 is the safest and most economical nuclear power plant available in the worldwide commercial marketplace, and is the only Generation III+ reactor to receive Design Certification from the U.S. Nuclear Regulatory Commission (NRC). The AP1000 features proven technology, innovative passive safety systems and offers: Unequalled safety, Economic competitiveness, Improved and more efficient operations. The AP1000 builds and improves upon the established technology of major components used in current Westinghouse-designed plants with proven, reliable operating experience over the past 50 years. These components include: Steam generators, Digital instrumentation and controls, Fuel, Pressurizers, Reactor vessels. Simplification was a major design objective for the AP1000. The simplified plant design includes overall safely systems, normal operating systems, the control room, construction techniques, and instrumentation and control systems. The result is a plant that is easier and less expensive to build, operate and maintain. The AP1000 design saves money and time with an accelerated construction time period of approximately 36 months, from the pouring of first concrete to the loading of fuel. Also, the innovative AP1000 features: 50% fewer safety-related valves, 80% less safety-related piping, 85% less control cable, 35% fewer pumps , 45% less seismic building volume. Eight AP1000 units under construction worldwide-Four units in China-Four units in the United States. (author)

  9. Testing of Solar Heated Domestic Hot Water System for Solahart Scandinavia ApS

    DEFF Research Database (Denmark)

    Andersen, Elsa

    1997-01-01

    The solar heating system marketed by Solahart Scandinavia ApS was tested in the Institutes test facility for SDHWsystems. The test results are described in the report.......The solar heating system marketed by Solahart Scandinavia ApS was tested in the Institutes test facility for SDHWsystems. The test results are described in the report....

  10. Containment integrity analysis for the (W) advanced AP900

    International Nuclear Information System (INIS)

    The consequences of accidents that occurred at Three Mile Island and Chernobyl and the lack of interest from utilities in committing to high powered, high maintenance light water reactor designs of the past have motivated the nuclear industry to develop smaller, lower powered, simplified designs. Simplified designs must employ more passive systems that require very low maintenance and rely on the basic laws of nature. These designs must not be limited only to the reactor, but must also include the containment building. The purpose of this paper is to discuss the design concepts and to verify the feasibility of the Westinghouse Passive Containment Cooling System (PCCS) design for a 900 MWe advanced passive reactor design (AP900) by presenting its response to a design basis large break Loss of Coolant Accident (LOCA). The mass and energy releases emanating from the design basis break were developed and a representative containment model was constructed. The COMPACT computer code, which is a multi-node program that solves the complete set of mass, energy and momentum equations, was used to determine the AP900 containment response. The PCCS design concept, the computer model, the analysis inputs, and the results of the study are discussed within this paper. (author). 2 refs., 9 figs

  11. Nuclear Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hogerton, John

    1964-01-01

    This pamphlet describes how reactors work; discusses reactor design; describes research, teaching, and materials testing reactors; production reactors; reactors for electric power generation; reactors for supply heat; reactors for propulsion; reactors for space; reactor safety; and reactors of tomorrow. The appendix discusses characteristics of U.S. civilian power reactor concepts and lists some of the U.S. reactor power projects, with location, type, capacity, owner, and startup date.

  12. AP600 large-break loss-of-collant-accident developmental assessment plan for TRAC-PF1/MOD2

    International Nuclear Information System (INIS)

    The Westinghouse AP600 reactor is an advanced pressurized water reactor with passive safety systems to protect the plant against possible accidents and transients. The design has been submitted to the U.S. NRC for design certification. The NRC has selected the Transient Reactor Analysis Code (TRAC)-PF1/MOD2 for performing large break loss-of coolant-accident (LBLOCA) analysis to support the certification effort. This document defines the tests to be used in the current phase of developmental assessment related to AP600 LBLOCA

  13. APS high heat load monochromator

    Energy Technology Data Exchange (ETDEWEB)

    Lee, W.K.; Mills, D.

    1993-02-01

    This document contains the design specifications of the APS high heat load (HHL) monochromator and associated accessories as of February 1993. It should be noted that work is continuing on many parts of the monochromator including the mechanical design, crystal cooling designs, etc. Where appropriate, we have tried to add supporting documentation, references to published papers, and calculations from which we based our decisions. The underlying philosophy behind performance specifications of this monochromator was to fabricate a device that would be useful to as many APS users as possible, that is, the design should be as generic as possible. In other words, we believe that this design will be capable of operating on both bending magnet and ID beamlines (with the appropriate changes to the cooling and crystals) with both flat and inclined crystal geometries and with a variety of coolants. It was strongly felt that this monochromator should have good energy scanning capabilities over the classical energy range of about 4 to 20 keywith Si (111) crystals. For this reason, a design incorporating one rotation stage to drive both the first and second crystals was considered most promising. Separate rotary stages for the first and second crystals can sometimes provide more flexibility in their capacities to carry heavy loads (for heavily cooled first crystals or sagittal benders of second crystals), but their tuning capabilities were considered inferior to the single axis approach.

  14. APS high heat load monochromator

    International Nuclear Information System (INIS)

    This document contains the design specifications of the APS high heat load (HHL) monochromator and associated accessories as of February 1993. It should be noted that work is continuing on many parts of the monochromator including the mechanical design, crystal cooling designs, etc. Where appropriate, we have tried to add supporting documentation, references to published papers, and calculations from which we based our decisions. The underlying philosophy behind performance specifications of this monochromator was to fabricate a device that would be useful to as many APS users as possible, that is, the design should be as generic as possible. In other words, we believe that this design will be capable of operating on both bending magnet and ID beamlines (with the appropriate changes to the cooling and crystals) with both flat and inclined crystal geometries and with a variety of coolants. It was strongly felt that this monochromator should have good energy scanning capabilities over the classical energy range of about 4 to 20 keywith Si (111) crystals. For this reason, a design incorporating one rotation stage to drive both the first and second crystals was considered most promising. Separate rotary stages for the first and second crystals can sometimes provide more flexibility in their capacities to carry heavy loads (for heavily cooled first crystals or sagittal benders of second crystals), but their tuning capabilities were considered inferior to the single axis approach

  15. Research on thermal hydraulic behavior of small-break LOCAs in AP1000

    International Nuclear Information System (INIS)

    Highlights: • A RELAP5 model for RCS and passive safety systems in AP1000 was developed. • A spectrum of cold leg small break LOCAs was analyzed. • The PCTs are far below the limit value of 1478 K and meet the safety criterion. • This article is useful for design and operation of AP1000 and other plants. -- Abstract: As a Generation III+ reactor that received Final Design Approval by U.S. NRC, AP1000 employs a series of nature forces, such as gravity, natural circulation and compressed gas, to enhance plant safety. Although plenty of work has been done around AP600 and its updated version AP1000 both experimentally and theoretically in the past few decades, thermal hydraulic behavior of small break LOCAs in AP1000 has not been fully understood and further studies are still required. In the present study, the response of AP1000 to a spectrum of cold leg small break LOCAs is simulated and analyzed using RELAP5/MOD3.4, including 2-in. break, 4-in. break, 8-in. break as well as 10-in. break which approaches the upper limit size for small break LOCAs in AP1000. Based on the calculation results, it indicates that the passive safety systems employed by AP1000, including CMTs, ACCs, IRWST, PRHRS and ADS, combine to provide continuous passive safety injection and residual heat removal. During cold leg small break LOCAs, the core uncovery and fuel heat up do not occur. The peak cladding temperatures (PCTs) during the accident process are far below the Appendix K limit value of 1478 K/2200 °F and meet the safety criterion. Results show that the accidental consequence can be mitigated effectively and thus the safety of AP1000 during cold leg small break LOCAs is proven

  16. Implementation of 1E digital platform common Q in AP1000 DCS

    International Nuclear Information System (INIS)

    As a generation III passive PWR, AP1000 is advanced and economical. This article emphasizes on the hardware and software description of Common Q, which is the 1E digital platform implemented in AP1000 DCS. And also it gives a introduction of implementation of Common Q in Reactor Protection and Safety Monitoring System and Past Accident Monitoring System. This article gives a brief comparison between Common Q and TXS. TXS is the 1E digital platform used in LingAo Phase II Nuclear Power Station and TaiShan Nuclear Power Station, which is generation III Evolutionary Pressurized Water Reactor. The aim of this article is to present both Common Q (used in AP1000) and TXS (used in EPR) to people who are involved in design, complete of system, star-up of Nuclear Power Station DCS. (authors)

  17. Tank 241-AP-106, Grab samples, 6AP-98-1, 6AP-98-2 and 6AP-98-3 Analytical results for the final report

    International Nuclear Information System (INIS)

    This document is the final report for tank 241-AP-106 grab samples. Three grab samples 6AP-98-1, 6AP-98-2 and 6AP-98-3 were taken from riser 1 of tank 241-AP-106 on May 28, 1998 and received by the 222-S Laboratory on May 28, 1998. Analyses were performed in accordance with the ''Compatability Grab Sampling and Analysis Plan'' (TSAP) (Sasaki, 1998) and the ''Data Quality Objectives for Tank Farms Waste Compatability Program (DQO). The analytical results are presented in the data summary report. No notification limits were exceeded. The request for sample analysis received for AP-106 indicated that the samples were polychlorinated biphenyl (PCB) suspects. The results of this analysis indicated that no PCBs were present at the Toxic Substance Control Act (TSCA) regulated limit of 50 ppm. The results and raw data for the PCB analysis are included in this document

  18. APS: Lighting up the future

    International Nuclear Information System (INIS)

    Work on the Advanced Photon Source (APS) at Argonne National Laboratory (ANL) involves the construction and supporting research and development for a national user facility for synchrotron radiation research in the x-ray region. The facility, when operational in 1997, will provide super-intense x-ray beams for many areas of basic research and will serve the entire US x-ray research community of several thousand users. This paper describes the pertinent features of the design, construction and planned operation of the facility; and the impact quality has had in these areas. In addition, the introduction of several quality management techniques such as total quality management, reliability/availability planning, and user interface are discussed concerning their status and success

  19. On AP-property of Function Spaces

    Institute of Scientific and Technical Information of China (English)

    SHEN Rong-xin

    2012-01-01

    In this paper,it is discussed the AP-property of function spaces.We prove that for any compact network α for a space X which is closed under finite unions,(1) if Cα(X) is an AP-space and X is paracompact,then X is a Hurewicz space; (2) if Cα (X) is an AP-space which has countable tightness,then Cα(X) is discretely generated.

  20. AP600-passive containment cooling system structure design and analysis

    International Nuclear Information System (INIS)

    The purpose of this paper is to present the design and analysis activities for the structures of AP 600 passive containment cooling system (PCCS). This design is being performed jointly by Ansaldo and Westinghouse as a part of the AP 600 program under the overall leadership of Westinghouse. The AP 600 is a 600 MWe advanced light water reactor that is being designed with passive safety features. The PCCS structures consist of the shield building roof which includes a 400,000 gallon water tank and the PCCS air baffles which direct air flow over the outside of a steel containment vessel to provide the passive cooling of the containment. Two different configurations have been investigated for the shield building roof. One is a flat roof with deep steel girders and a concrete slab with the water tank integral with the steel girders. Another is a conical concrete roof with a steel-lined reinforced concrete tank. Three different options for the water tank have been analyzed. The function of the air baffles is to provide a pathway for natural circulation in a postulated design basis event resulting in large energy release into a containment. (K.I.)

  1. OLP embedment design method research for AP1000 nuclear plant

    International Nuclear Information System (INIS)

    Background: One of the most advanced nuclear power technology, the first AP1000 reactor is under construction in China. Modularization is one of the main characteristics for AP1000 nuclear plant building. Module wall with steel face plate is used instead of reinforced concrete structure wall. A number of OLP embedments need to be installed into the module wall to connect other structures such as pipes, equipment, operation platforms and any other component attached to the module wall. Therefore, the design of embedment is very important in AP1000 structural design. Purpose: A finite element analysis method and tool for embedment design is needed for convenience. Methods: This paper applies the self-developed GTStrudl command template and VBA macro program for embedment capacity calculation and evaluation based on Microsoft Excel to the embedment design. Results: A Microsoft Excel template for embedment design is developed. Conclusions: The analysis method and template brings reasonable results and may provide some help and use for reference for the engineering practice. (authors)

  2. AP calculus AB & BC crash course

    CERN Document Server

    Rosebush, J

    2012-01-01

    AP Calculus AB & BC Crash Course - Gets You a Higher Advanced Placement Score in Less Time Crash Course is perfect for the time-crunched student, the last-minute studier, or anyone who wants a refresher on the subject. AP Calculus AB & BC Crash Course gives you: Targeted, Focused Review - Study Only What You Need to Know Crash Course is based on an in-depth analysis of the AP Calculus AB & BC course description outline and actual AP test questions. It covers only the information tested on the exams, so you can make the most of your valuable study time. Written by experienced math teachers, our

  3. AP1000® SBLOCA simulations with TRACE code

    International Nuclear Information System (INIS)

    Highlights: • Assessment of AP1000 behavior in SBLOCA sequences. • Importance of CMTs and PRHR system for core cooling in case of small break sizes. • Well behavior of the plant in case of availability of half of the total ECCS because of DEDVI. - Abstract: The AP1000® is an advanced pressurized water reactor (PWR) design developed by Westinghouse which implements passive safety systems to provide core cooling in case of accident. The performing of such systems must be evaluated through the performance of experiments and simulations with a variety of thermal–hydraulic codes. This paper presents the results which has been obtained for different SBLOCA break sizes with the best estimate TRACE V5.0 patch 2 thermal–hydraulic code and their comparison with those obtained by Westinghouse with NOTRUMP code. The main results show that TRACE code predicts a similar trend in all sequences with some differences that are expected to be an issue of the more conservative models and hypothesis assumed in the SBLOCA licensing analysis performed with NOTRUMP. Some particular characteristics of this reactor are also shown in this paper such as the importance of core makeup tank (CMT) and passive residual heat removal (PRHR) system for core cooling in case of small break sizes and the behavior of the plant in case of availability of half of the total passive safety injection systems which is the case of the double-ended direct vessel injection line break (DEDVI)

  4. ELECTROCHEMICAL CORROSION TESTING OF TANKS 241-AN-102 & 241-AP-107 & 241-AP-108 IN SUPPORT OF ULTRASONIC TESTING

    Energy Technology Data Exchange (ETDEWEB)

    WYRWAS RB; DUNCAN JB

    2008-11-20

    This report presents the results of the corrosion rates that were measured using electrochemical methods for tanks 241-AN-102 (AN-102), 241-AP-107 (AP 107), and 241-AP-108 (AP-108) performed under test plant RPP-PLAN-38215. The steel used as materials of construction for AN and AP tank farms was A537 Class 1. Test coupons of A537 Class 1 carbon steel were used for corrosion testing in the AN-107, AP-107, and AP-108 tank waste. Supernate will be tested from AN-102, AP-107, and Ap-108. Saltcake testing was performed on AP-108 only.

  5. AP1000: Meeting economic goals in a competitive world. Annex 7

    International Nuclear Information System (INIS)

    In the U.S., conditions are becoming more favorable for considering the nuclear option again for new baseload generation. While oil and natural gas prices have risen, the cost of operating the existing fleet of nuclear plants has decreased. Furthermore, an advanced 1000 MWe nuclear plant that will be even more cost-competitive with fossil fuels and natural gas will be available by 2005. Westinghouse, in an effort to further improve on the AP600's cost competitiveness, has developed the AP1000, a two-loop, 1000 MWe, advanced pressurized water reactor (PWR) with passive safety features and extensive plant simplifications to enhance the construction, operation, and maintenance. Like the AP600, the AP1000 uses proven technology that builds on over 30 years of operating PWR experience. Westinghouse has completed design studies that demonstrate that it is feasible to increase the power output of the AP600 to at least 1000 MWe, maintaining its current design configuration and licensing basis. To maximize the cost savings, the AP1000 has been designed within the space constraints of the AP600, while retaining the credibility of proven components and substantial safety margins. The affect on the plant's overnight cost of the increased major components that is required to uprate the AP600 to 1000 MWe is small. This overall cost addition is on the order of 11 percent, while the overall power increase is almost 80 percent. This paper describes the changes made to uprate the AP600 and gives an overview of the plant design. (author)

  6. Coaching Strategies for AP: Building a Successful AP European History Program

    Science.gov (United States)

    Fornaciari, Jim

    2014-01-01

    The October 2013 special issue of "Social Education" dealt with almost all AP social studies subjects, but omitted AP European History. This is one of the most fascinating AP subjects for students and teachers alike. In this article, the author shares his experiences since hewas given the responsibility of building his school's…

  7. The status of APS, BESSRC, and NEET.

    Energy Technology Data Exchange (ETDEWEB)

    Ahmad, I.; Dunford, R. W.; Esbensen, H.; Gemmell, D. S.; Kanter, E. P.; Kraessig, B.; Rutt, U.; Southworth, S. H.

    1999-03-10

    We present a brief summary of the current status of the Advanced Photon Source (APS) at Argonne National Laboratory and of the facilities at two of the APS sectors operated by the Basic Energy Sciences Synchrotrons Radiation Center (BESSRC). This is followed by a report on recent measurements at BESSRC on the phenomenon of Nuclear Excitation by Electronic Transition (NEET).

  8. The status of APS, BESSRC, and NEET

    International Nuclear Information System (INIS)

    We present a brief summary of the current status of the Advanced Photon Source (APS) at Argonne National Laboratory and of the facilities at two of the APS sectors operated by the Basic Energy Sciences Synchrotrons Radiation Center (BESSRC). This is followed by a report on recent measurements at BESSRC on the phenomenon of Nuclear Excitation by Electronic Transition (NEET)

  9. AP Courses Get Audited for Quality

    Science.gov (United States)

    Ashford, Ellie

    2007-01-01

    As the college admissions process has gotten much more competitive, the number of high school students taking Advanced Placement (AP) courses has soared. At the same time, policymakers and education leaders seek to get more minorities and students not on the college track to sign up for AP and other rigorous classes. But as high schools have…

  10. AP-42 ADDITIONS AND REVISIONS - WILDLAND FIRES

    Science.gov (United States)

    This project is aimed at consolidating, selecting, and disseminating the most appropriate data and methods for estimating air emissions from wildfires and prescribed burns. The product will replace a current section of AP-42, but may not take the precise form of an AP-42 secti...

  11. Safety features and research needs of westinghouse advanced reactors

    International Nuclear Information System (INIS)

    The three Westinghouse advanced reactors - AP600, AP1000 and IRIS - are at different levels of readiness. AP600 has received a Design Certification, its larger size version AP1000 is currently in the design certification process and IRIS has just completed its conceptual design and will initiate soon a licensing pre-application. The safety features of the passive designs AP600/AP1000 are presented, followed by the features of the more revolutionary IRIS, a small size modular integral reactor. A discussion of the IRIS safety by design approach is given. The AP600/AP1000 design certification is backed by completed testing and development which is summarized, together with a research program currently in progress which will extend AP600 severe accident test data to AP1000 conditions. While IRIS will of course rely on applicable AP600/1000 data, a very extensive testing campaign is being planned to address all the unique aspects of its design. Finally, IRIS plans to use a risk-informed approach in its licensing process. (authors)

  12. APS undulator radiation: First results

    International Nuclear Information System (INIS)

    The first undulator radiation has been extracted from the Advanced Photon Source (APS). The results from the characterization of this radiation are very satisfactory. With the undulator set at a gap of 15.8 mm (K=1.61), harmonics as high as the 17th were observed using a crystal spectrometer. The angular distribution of the third-harmonic radiation was measured, and the source was imaged using a zone plate to determine the particle beam emittance. The horizontal beam emittance was found to be 6.9 ± 1.0 nm-rad, and the vertical emittance coupling was found to be less than 3%. The absolute spectral flux was measured over a wide range of photon energies, and it agrees remarkably well with the theoretical calculations based on the measured undulator magnetic field profile and the measured beam emittance. These results indicate that both the emittance of the electron beam and the undulator magnetic field quality exceed the original specifications

  13. The use of thioglycolate to distinguish between 3' AP (apurinic/apyrimidinic) endonucleases and AP lyases.

    OpenAIRE

    Bricteux-Grégoire, S; Verly, W G

    1989-01-01

    Addition of thioglycolate and DEAE-Sephadex chromatography were used to analyze the cleavage of the C(3')-O-P bond 3' to AP (apurinic/apyrimidinic) sites in DNA and to distinguish between a mechanism of hydrolysis (which would allow the nicking enzyme to be called 3' AP endonuclease) or beta-elimination (so that the nicking enzyme should be called AP lyase). For this purpose, DNA labelled in the AP sites was first cleaved by rat-liver AP endonuclease, then with the 3' nicking catalyst in the ...

  14. Effect of AP1000 steel containment thickness of heat transfer performance

    International Nuclear Information System (INIS)

    AP1000 is one of the safest advanced power water reactors. Comparing with generation Ⅱ power plant, an obvious character of AP1000 is using steel containment instead of concrete containment. The steel containment is very important in the whole heat transfer process. The thickness of containment was studied using WGOTHIC to establish long term air cooling model and the relationship between the heat transfer performance and containment thickness was found. The results show that the safety is raised while increasing the containment thickness in a certain range. It is a reference for the power plant with steel containment design. (authors)

  15. AP1000® Large-Break LOCA BEPU analysis with TRACE code

    International Nuclear Information System (INIS)

    Highlights: • Assessment of AP1000 behavior in LBLOCA sequences. • AP1000 LBLOCA comparison against standard PWR-3L. • TRACE-DAKOTA application to BEPU analysis. - Abstract: The AP1000® is an advanced Pressurized Water Reactor (PWR) design developed by Westinghouse which implements passive safety systems to provide core cooling in case of accident. The development of best-estimate codes produced the evolution of conservative safety analysis towards the so-called best-estimate plus uncertainty (BEPU) analysis in order to obtain more realistic results and larger safety margins. In this sense, Westinghouse used for AP1000 Large Break Loss of Coolant Accident (LBLOCA) the so-called Automated Statistical Treatment of Uncertainty Method (ASTRUM) which was developed to address this kind of BEPU analysis. This paper presents a verification of the AP1000 LBLOCA BEPU analysis by means of TRACE V5.0 patch 2 thermal–hydraulic code with the support of DAKOTA code for uncertainty calculations. The results obtained show lower values for the maximum PCT than the ones obtained by Westinghouse. In both cases the results show that AP1000 can mitigate effectively the occurrence of a postulate LBLOCA and to meet the 10CFR50.46 PCT acceptance criteria with enough margin

  16. Tank 241-AP-107, grab samples, 7AP-99-1, 7AP-99-3 and 7AP-99-4 analytical results for the final report

    Energy Technology Data Exchange (ETDEWEB)

    BELL, K.E.

    1999-08-12

    This document is the format IV, final report for the tank 241-AP-107 (AP-107) grab samples taken in May 1999 to address waste compatibility concerns. Chemical, radiochemical, and physical analyses on the tank AP-107 samples were performed as directed in Compatibility Grab Sampling and Analysis Plan for Fiscal year 1999. Any deviations from the instructions provided in the tank sampling and analysis plan (TSAP) were discussed in this narrative. Interim data were provided earlier to River Protection Project (RPP) personnel, however, the data presented here represent the official results. No notification limits were exceeded.

  17. AP English language & composition crash course

    CERN Document Server

    Hogue, Dawn

    2012-01-01

    AP English Language & Composition Crash Course - Gets You a Higher Advanced Placement Score in Less Time Crash Course is perfect for the time-crunched student, the last-minute studier, or anyone who wants a refresher on the subject. AP English Language & Composition Crash Course gives you: Targeted, Focused Review - Study Only What You Need to Know Crash Course is based on an in-depth analysis of the AP English Language & Composition course description outline and actual Advanced Placement test questions. It covers only the information tested on the exam, so you can make the most of your valua

  18. Tank 241-AP-107, grab samples, 7AP-99-1, 7AP-99-3 and 7AP-99-4 analytical results for the final report

    International Nuclear Information System (INIS)

    This document is the format IV, final report for the tank 241-AP-107 (AP-107) grab samples taken in May 1999 to address waste compatibility concerns. Chemical, radiochemical, and physical analyses on the tank AP-107 samples were performed as directed in Compatibility Grab Sampling and Analysis Plan for Fiscal year 1999. Any deviations from the instructions provided in the tank sampling and analysis plan (TSAP) were discussed in this narrative. Interim data were provided earlier to River Protection Project (RPP) personnel, however, the data presented here represent the official results. No notification limits were exceeded

  19. Tank 241-AP-106, Grab samples, 6AP-98-1, 6AP-98-2 and 6AP-98-3 Analytical results for the final report

    Energy Technology Data Exchange (ETDEWEB)

    FULLER, R.K.

    1999-02-23

    This document is the final report for tank 241-AP-106 grab samples. Three grab samples 6AP-98-1, 6AP-98-2 and 6AP-98-3 were taken from riser 1 of tank 241-AP-106 on May 28, 1998 and received by the 222-S Laboratory on May 28, 1998. Analyses were performed in accordance with the ''Compatability Grab Sampling and Analysis Plan'' (TSAP) (Sasaki, 1998) and the ''Data Quality Objectives for Tank Farms Waste Compatability Program (DQO). The analytical results are presented in the data summary report. No notification limits were exceeded. The request for sample analysis received for AP-106 indicated that the samples were polychlorinated biphenyl (PCB) suspects. The results of this analysis indicated that no PCBs were present at the Toxic Substance Control Act (TSCA) regulated limit of 50 ppm. The results and raw data for the PCB analysis are included in this document.

  20. AP 600 - In containment refueling water storage tank (IRWST) hydrodynamic analysis

    International Nuclear Information System (INIS)

    The AP600 is a 600 MWe Advanced Light Water Reactor that is being designed with passive safety features including an automatic depressurization system (ADS). During emergency conditions some of the ADS valves discharge into the in-containment refueling water storage tank (IRWST) under water through a sparger, producing hydrodynamic loads on the tank walls and equipment. The purpose of this paper is to present the IRWST hydrodynamic analyses, jointly performed by Ansaldo and Westinghouse, as part of the AP600 program, under Westinghouse's overall leadership, in conjunction with sparger tests conducted on a test tank model. An analytical procedure to predict hydrodynamic loads imposed on the AP600 IRWST tank from ADS discharges has been validated by a comparison with test tank measurements; the appropriate inclusion of fluid structure interaction effects allows significant pressure attenuations from the discharge region and indicates that relatively low structural effects are produced on tank main structures from induced wall pressures

  1. Fourth Generation Reactor Concepts

    International Nuclear Information System (INIS)

    Concerns over energy resources availability, climate changes and energy supply security suggest an important role for nuclear energy in future energy supplies. So far nuclear energy evolved through three generations and is still evolving into new generation that is now being extensively studied. Nuclear Power Plants are producing 16% of the world's electricity. Today the world is moving towards hydrogen economy. Nuclear technologies can provide energy to dissociate water into oxygen and hydrogen and to production of synthetic fuel from coal gasification. The introduction of breeder reactors would turn nuclear energy from depletable energy supply into an unlimited supply. From the early beginnings of nuclear energy in the 1940s to the present, three generations of nuclear power reactors have been developed: First generation reactors: introduced during the period 1950-1970. Second generation: includes commercial power reactors built during 1970-1990 (PWR, BWR, Candu, Russian RBMK and VVER). Third generation: started being deployed in the 1990s and is composed of Advanced LWR (ALWR), Advanced BWR (ABWR) and Passive AP600 to be deployed in 2010-2030. Future advances of the nuclear technology designs can broaden opportunities for use of nuclear energy. The fourth generation reactors are expected to be deployed by 2030 in time to replace ageing reactors built in the 1970s and 1980s. The new reactors are to be designed with a view of the following objectives: economic competitiveness, enhanced safety, minimal radioactive waste production, proliferation resistance. The Generation IV International Forum (GIF) was established in January 2000 to investigate innovative nuclear energy system concepts. GIF members include Argentina, Brazil, Canada, Euratom, France Japan, South Africa, South Korea, Switzerland, United Kingdom and United States with the IAEA and OECD's NEA as permanent observers. China and Russia are expected to join the GIF initiative. The following six systems

  2. Analysis of safety margin of in-vessel retention for AP1000

    International Nuclear Information System (INIS)

    In-vessel retention (IVR) of core melt is a key severe accident management strategy adopted by most operating nuclear power plants and advanced light water reactors (ALWRs), AP600, AP1000, etc. External reactor vessel cooling (ERVC) is a novel severe accident management for IVR analysis. In present study, IVR analysis code in severe accident (IVRASA) has been developed to evaluate the safety margin of IVR in AP1000 with anticipative depressurization and reactor cavity flooding in severe accident. For, IVRASA, the point estimate procedure has been developed for modeling the steady-state endpoint of two core melt configurations: Configuration I and Configuration II. The results of benchmark calculations of AP600 by IVRASA were consistent with those of the UCSB and INEEL. Then, IVRASA is used to calculate the heat transfer process caused by two core melt configurations of AP1000. The results of calculations of Configuration I indicate that the heat flux remains below the critical heat flux (CHF), however, the sensitivity calculations show that the heat flux in the metallic layer could exceed the CHF because of the focusing effect due to the thin metallic layer. On the other hand, the results of calculations of Configuration II suggest that the thermal failure of the lower head at the bottom location is highly unlikely, but the heat flux in light metallic layer could be higher than that of base case due to the portion of metal partitioning into the lower head. This work also investigated the effect of the uncertainties of the CHF correlations on the analysis of IVR.

  3. Dynamic property test study for AP1000 core shroud in air

    International Nuclear Information System (INIS)

    Background: Core shroud is an important assembly, which forms the lateral periphery of the core inside the core barrel. Purpose: To carry out a dynamic property test on a core shroud mockup (1:1) at the damping, natural frequency and the corresponding vibration mode of AP1000 reactor internal core shroud assembly in air. Methods: The multi-input multi-output (MIMO) test method was used in this modal test. Results: By such test, the first six mode natural frequencies, damping and vibration modes of the core shroud assembly were obtained. Conclusions: The test results would be used to offer natural parameters of the core shroud assembly for AP1000 reactor equipment system model and flow-induce vibration analysis of the core shroud assembly. (authors)

  4. AP1000{sup R} severe accident features and post-Fukushima considerations

    Energy Technology Data Exchange (ETDEWEB)

    Scobel, J. H.; Schulz, T. L.; Williams, M. G. [Westinghouse Electric Company, LLC, 1000 Westinghouse Dr., Cranberry Township, PA 16066 (United States)

    2012-07-01

    The AP1000{sup R} passive nuclear power plant is uniquely equipped to withstand an extended station blackout scenario such as the events following the earthquake and tsunami at Fukushima without compromising core and containment integrity. The AP1000 plant shuts down the reactor, cools the core, containment and spent fuel pool for more than 3 days using passive systems that do not require AC or DC power or operator actions. Following this passive coping period, minimal operator actions are needed to extend the operation of the passive features to 7 days using installed equipment. To provide defense-in-depth for design extension conditions, the AP1000 plant has engineered features that mitigate the effects of core damage. Engineered features retain damaged core debris within the reactor vessel as a key feature. Other aspects of the design protect containment integrity during severe accidents, including unique features of the AP1000 design relative to passive containment cooling with water and air, and hydrogen management. (authors)

  5. Analysis of the automatic depressurization system (ADS) tests for the AP600 design

    International Nuclear Information System (INIS)

    The AP600 is a Westinghouse advanced pressurized water reactor (PWR) designed with passive plant safety features that rely on natural driving forces, such as gravity, and natural circulation which allows significant simplification of the plant systems equipment and operation. As part of the passive safety concept, the AP600 utilizes an Automatic Depressurization System (ADS) to depressurize the Reactor Coolant System (RCS) allowing long-term gravity injection to be initiated and maintained for passive reflood and long term core cooling. The ADS design consists of four flow paths, two of which are connected to the top of the pressurizer and a flow path from each of the two RCS hot legs. During a postulated accident, the two flow paths from the hot legs discharge directly to containment. The two paths from the pressurizer discharge steam and/or water from the RCS into the In-containment Refueling Water Storage Tank (IRWST) through spargers located underwater where the steam is normally condensed with no increase in containment pressure or temperature. The ADS tests are one part of the planned AP600 Westinghouse test program for the passive core cooling system (PXS). The ADS tests are full-scale simulations of AP600 ADS components. The ADS tests provide dynamic performance data of the ADS for use in computer code validation and design verification

  6. Offsite dose risk quantification analysis for AP1000 nuclear power plant

    International Nuclear Information System (INIS)

    In order to estimate the potential offsite effect caused by severe accidents of AP1000 nuclear power plant, radiation dose risk was quantified, which takes into account six representative release categories. Atmospheric transport with airborne radioactive material was simulated by MACCS code. The results show that acute red marrow dose risk at the site boundary is 1.96 X 10-7 Sv/ (reactor · year), which mainly results from containment bypass release (BP). The early health effect risks are 10-10-10-9 Sv/ (reactor · year), and the risks decrease obviously with the increase of distance from reactor. Population whole-body effective dose risk is 6.94 X 10-4 person · Sv/ (reactor · year), and the corresponding cancer fatality risk is quite low. The study result also indicates that timely evacuation after the nuclear accident can reduce public dose risk significantly. (authors)

  7. Analysis of large break LOCA in the NPP AP-600: second phase

    International Nuclear Information System (INIS)

    Analysis of large break LOCA in nuclear power plant AP-600 was done by reactor computational simulation using a computer program COBRA IV-I. Large break LOCA is considered as the severest hypothetical accident in the pressurized water reactor. 1/8 symmetrical core is used in the calculation model, and peak cladding temperature is monitored as a LOCA accident criteria. To do this analysis, it was required such system data during the transient condition from the Westinghouse calculation. Calculation results of peak cladding temperature during LOCA is 1500oF, this calculation showed that there is difference <15% with the Westinghouse calculation

  8. Generalities about nuclear reactors

    International Nuclear Information System (INIS)

    From Zoe, the first nuclear reactor, till the current EPR, the French nuclear industry has always advanced by profiting from the feedback from dozens of years of experience and operations, in particular by drawing lessons from the most significant events in its history, such as the Fukushima accident. The new generations of reactors must improve safety and economic performance so that the industry maintain its legitimacy and its share in the production of electricity. This article draws the history of nuclear power in France, gives a brief description of the pressurized water reactor design, lists the technical features of the different versions of PWR that operate in France and compares them with other types of reactors. The feedback experience concerning safety, learnt from the major nuclear accidents Three Miles Island (1979), Chernobyl (1986) and Fukushima (2011) is also detailed. Today there are 26 third generation reactors being built in the world: 4 EPR (1 in Finland, 1 in France and 2 in China); 2 VVER-1200 in Russia, 8 AP-1000 (4 in China and 4 in the Usa), 8 APR-1400 (4 in Korea and 4 in UAE), and 4 ABWR (2 in Japan and 2 in Taiwan)

  9. Tank 241-AP-107, grab samples 7AP-97-1, 7AP-97-2 and 7AP-97-3 analytical results for the final report

    International Nuclear Information System (INIS)

    This document is the final report for tank 241-AP-107 grab samples. Three grab samples were collected from riser 1 on September 11, 1997. Analyses were performed on samples 7AP-97-1, 7AP-97-2 and 7AP-97-3 in accordance with the Compatibility Grab Sampling and Analysis Plan (TSAP) (Sasaki, 1997) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) (Rev. 1: Fowler, 1995; Rev. 2: Mulkey and Nuier, 1997). The analytical results are presented in the data summary report (Table 1). A notification was made to East Tank Farms Operations concerning low hydroxide in the tank and a hydroxide (caustic) demand analysis was requested. The request for sample analysis (RSA) (Attachment 2) received for AP-107 indicated that the samples were polychlorinated biphenyl (PCB) suspects. Therefore, prior to performing the requested analyses, aliquots were made to perform PCB analysis in accordance with the 222-S Laboratory administrative procedure, LAP-101-100. The results of this analysis indicated that no PCBs were present at 50 ppm and analysis proceeded as non-PCB samples. The results and raw data for the PCB analysis will be included in a revision to this document. The sample breakdown diagrams (Attachment 1) are provided as a cross-reference for relating the tank farm customer identification numbers with the 222-S Laboratory sample numbers and the portion of sample analyzed

  10. Tank 241-AP-107, grab samples 7AP-97-1, 7AP-97-2 and 7AP-97-3 analytical results for the final report

    Energy Technology Data Exchange (ETDEWEB)

    Steen, F.H.

    1997-12-22

    This document is the final report for tank 241-AP-107 grab samples. Three grab samples were collected from riser 1 on September 11, 1997. Analyses were performed on samples 7AP-97-1, 7AP-97-2 and 7AP-97-3 in accordance with the Compatibility Grab Sampling and Analysis Plan (TSAP) (Sasaki, 1997) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) (Rev. 1: Fowler, 1995; Rev. 2: Mulkey and Nuier, 1997). The analytical results are presented in the data summary report (Table 1). A notification was made to East Tank Farms Operations concerning low hydroxide in the tank and a hydroxide (caustic) demand analysis was requested. The request for sample analysis (RSA) (Attachment 2) received for AP-107 indicated that the samples were polychlorinated biphenyl (PCB) suspects. Therefore, prior to performing the requested analyses, aliquots were made to perform PCB analysis in accordance with the 222-S Laboratory administrative procedure, LAP-101-100. The results of this analysis indicated that no PCBs were present at 50 ppm and analysis proceeded as non-PCB samples. The results and raw data for the PCB analysis will be included in a revision to this document. The sample breakdown diagrams (Attachment 1) are provided as a cross-reference for relating the tank farm customer identification numbers with the 222-S Laboratory sample numbers and the portion of sample analyzed.

  11. The NuStart AP1000 Compact Control Room Implementation

    International Nuclear Information System (INIS)

    The nuclear power industry in the United States is experiencing renewed optimism that new nuclear power plants may be constructed in the foreseeable future. Presently a number of utilities in the U.S. are considering new nuclear plant construction. Among the reasons supporting the industry's optimism is the formation of the NuStart Energy Consortium. This consortium of leading energy companies, including Westinghouse Electric Company, is working with the U.S. Department of Energy to demonstrate and test the new licensing process for obtaining a Combined Construction and Operating License (COL) for an advanced light water reactor (ALWR). One ALWR design for which the NuStart Energy Consortium is pursuing a COL application is Westinghouse's passive AP1000. AP1000 received its Final Design Approval from the USNRC in the Fall of 2004 and was granted Design Certification by the NRC on December 30, 2005. A key element of the AP1000 COL application will be to close out Design Certification COL items related to the Main Control Room (MCR) and Human System Interface (HSI) design. During the AP1000 design certification licensing efforts, a control room and HSI design process was submitted and approved. Realizing that Instrumentation and Control (I and C) and HSI technology changes rapidly, Westinghouse chose to defer the detailed design of the control room and operator interfaces. This allows the latest technology to be used when a plant is actually going to be built. To fulfill the COL items for the upcoming application Westinghouse is performing a comprehensive Human Factors Engineering program in conjunction with development of an advanced set of HSI resources for a compact control room. This paper will discuss human factors program elements completed to date and the efforts currently in progress to complete the remaining elements. It will also describe the design progress for each HSI resource including a Wall Panel Information System, computerized procedure system

  12. Building an AP Social Studies Program with Non-Traditional AP Students

    Science.gov (United States)

    Ashmead, Amanda; Blanchette, Sue

    2013-01-01

    Equal access to education, that is to a high quality education, has increasingly come to mean access to an Advanced Placement program. In recent years, there has been steady attention paid to opening access to AP programs. The 9th annual College Board report (2013) stated "students who succeed on an AP Exam during high school typically…

  13. A note on weighted Ap(G)-modules

    OpenAIRE

    ÖZTOP, Serap

    2011-01-01

    Let G be a locally compact abelian group and w be a weight function on G. In this paper, we show that the space Ap,w(G) is a Banach module over the Figà-Talamanca Herz algebra Ap(G) and study the multiplier space from Ap(G) to Ap,w(G).

  14. Slotted Aloha with multi-AP diversity and APS transmit beamforming

    Directory of Open Access Journals (Sweden)

    Zheng Di

    2011-01-01

    Full Text Available Abstract Slotted Aloha is an effective random access protocol and can also be an important element of more advanced media access protocols. This paper investigates slotted Aloha in a radio environment with multiple access points. Specifically, we examine the impact of multi-access-point (multi-AP diversity on the performance of slotted Aloha. The paper considers both omni-directional (OM and beamforming (BF antennas at transmission nodes. This leads to the investigation and comparison of four different network scenarios, i.e., OM with multi-AP diversity, OM without multi-AP diversity, BF with multi-AP diversity and BF without multi-AP diversity. Performance evaluations and comparisons are presented in terms of throughput and average packet delay.

  15. Ectopic expression of FaesAP3, a Fagopyrum esculentum (Polygonaceae) AP3 orthologous gene rescues stamen development in an Arabidopsis ap3 mutant.

    Science.gov (United States)

    Fang, Zheng-wu; Qi, Rui; Li, Xiao-fang; Liu, Zhi-xiong

    2014-10-25

    Arabidopsis thaliana APETALA3 (AP3) and Antirrhinum majus DEFICIENS (DEF) MADS box genes are required to specify petal and stamen identity. AP3 and DEF are members of the euAP3 lineage, which arose by gene duplication coincident with radiation of the core eudicots. In order to investigate the molecular mechanisms underlying organ development in early diverging clades of core eudicots, we isolated and identified an AP3 homolog, FaesAP3, from Fagopyrum esculentum (buckwheat, Polygonaceae), a multi-food-use pseudocereal with healing benefits. Protein sequence alignment and phylogenetic analyses revealed that FaesAP3 grouped into the euAP3 lineage. Expression analysis showed that FaesAP3 was transcribed only in developing stamens, and differed from AP3 and DEF, which expressed in developing petals and stamens. Moreover, ectopic expression of FaesAP3 rescued stamen development without complementation of petal development in an Arabidopsis ap3 mutant. Our results suggest that FaesAP3 is involved in the development of stamens in buckwheat. These results also suggest that FaesAP3 holds some potential for biotechnical engineering to create a male sterile line of F. esculentum. PMID:25149019

  16. Axial power monitoring uncertainty in the Savannah River Reactors

    International Nuclear Information System (INIS)

    The results of this analysis quantified the uncertainty associated with monitoring the Axial Power Shape (APS) in the Savannah River Reactors. Thermocouples at each assembly flow exit map the radial power distribution and are the primary means of monitoring power in these reactors. The remaining uncertainty in power monitoring is associated with the relative axial power distribution. The APS is monitored by seven sensors that respond to power on each of nine vertical Axial Power Monitor (APM) rods. Computation of the APS uncertainty, for the reactor power limits analysis, started with a large database of APM rod measurements spanning several years of reactor operation. A computer algorithm was used to randomly select a sample of APSs which were input to a code. This code modeled the thermal-hydraulic performance of a single fuel assembly during a design basis Loss-of Coolant Accident. The assembly power limit at Onset of Significant Voiding was computed for each APS. The output was a distribution of expected assembly power limits that was adjusted to account for the biases caused by instrumentation error and by measuring 7 points rather than a continuous APS. Statistical analysis of the final assembly power limit distribution showed that reducing reactor power by approximately 3% was sufficient to account for APS variation. This data confirmed expectations that the assembly exit thermocouples provide all information needed for monitoring core power. The computational analysis results also quantified the contribution to power limits of the various uncertainties such as instrumentation error

  17. Plyler Prize and APS Fellow Introductions

    Science.gov (United States)

    Nathanson, Gilbert

    2014-03-01

    The Division of Chemical Physics is delighted to announce the 2013 APS Fellows sponsored by DCP and to honor the 2014 Earl K. Plyler Prize Award winner. The new APS Fellows are: Ilan Benjamin, Hua Guo, Manos Mavrikakis, Josef Paldus, Joern Siepmann, Hans-Peter Steinrueck, Douglas Tobias, Angela Wilson, and Yijing Yan. The citations for each awardee will be read out loud. I will also introduce Prof. Lai-Sheng Wang of the Department of Chemistry at Brown University, who was awarded the 2014 Plyler Prize for Molecular Spectroscopy and Dynamics. Please come learn about these extraordinary scientists during this prize session. Prof. Wang's Plyler Prize talk will follow immediately after this introduction. For more information, see http://www.aps.org/units/dcp/.

  18. N Reactor

    Data.gov (United States)

    Federal Laboratory Consortium — The last of Hanfordqaodmasdkwaspemas7ajkqlsmdqpakldnzsdflss nine plutonium production reactors to be built was the N Reactor.This reactor was called a dual purpose...

  19. Mechanical equipment classification research of AP1000 nuclear units

    International Nuclear Information System (INIS)

    According to the design features of AP1000, the AP1000 classification definition and seismic classification is described and analyzed. The characteristics of AP1000 mechanical equipment classification list is concluded for safety, seismic and manufacture classification. Through comparing the AP1000 classification and M310 classification, the questions perhaps met are found during the mechanical equipment classification of AP1000 nuclear power plants design and construction in China at future. Finally solution plans are given aiming at the above questions. (authors)

  20. An analysis of AP600 design features

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jong Kyoon; Jang, Moon Heui; Hwang, Yung Dong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)] [and others

    1994-01-01

    In the aspect of engineering, passive safety system concept has improved the safety degree of nuclear power plant. Therefore, the objective of this study is to check on the possibility of the capacity upgrade of nuclear power plant in the case of adopting the passive safety system concept of AP 600. The characteristics of AP 600 are the advanced functions in ECCS, heat removal of containment building and residual heat removal under the passive safety system concept. The result of this study will become the basic data of capacity upgrade of nuclear power plant and will be widely used in second year project. (Author).

  1. Research update : Atmospheric pressure spatial atomic layer deposition of ZnO thin films : reactors, doping and devices

    OpenAIRE

    Hoye, Robert L.Z.; David Muñoz-Rojas; Nelson, Shelby F.; Andrea Illiberi; Paul Poodt; Fred Roozeboom; MacManus-Driscoll, Judith L

    2015-01-01

    Atmospheric pressure spatial atomic layer deposition (AP-SALD) has recently emerged as an appealing technique for rapidly producing high quality oxides. Here, we focus on the use of AP-SALD to deposit functional ZnO thin films, particularly on the reactors used, the film properties, and the dopants that have been studied. We highlight how these films are advantageous for the performance of solar cells, organometal halide perovskite light emitting diodes, and thin-film transistors. Future AP-S...

  2. Tank 241-AP-107 tank characterization plan

    International Nuclear Information System (INIS)

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, WHC 222-S Laboratory, and PNL 325 Analytical Chemistry Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples from tank 241-AP-107

  3. 2000 Johnston Site 3A-P

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — Underwater Site 3A-P was established at Johnston Atoll by Dr. James Maragos, U.S. Fish & Wildlife Service, on July 3, 2000. With a start point (meter 0) at...

  4. 2000 Johnston Site 2A-P

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — Underwater Site 2A-P was established at Johnston Atoll by Dr. James Maragos, U.S. Fish & Wildlife Service, on June 30, 2000. With a start point (meter 0) at...

  5. 2000 Johnston Site 1A-P

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — Underwater Site 1A-P was established at Johnston Atoll by Dr. James Maragos, U.S. Fish & Wildlife Service, on June 29, 2000. With a start point (meter 0) at...

  6. 2006 Johnston Site 1A-P

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — Underwater Site 1A-P was established at Johnston Atoll by Dr. James Maragos, U.S. Fish & Wildlife Service, on June 29, 2000. With a start point (meter 0) at...

  7. The Demographic Wave: Rethinking Hispanic AP Trends

    Science.gov (United States)

    Edwards, Kelcey; Sawtell, Ellen

    2013-01-01

    Presented at the Advanced Placement Annual Conference (APAC) in Las Vegas, NV in July 2013. This presentation reviews new research examining the AP® experience of Hispanic graduates over the past decade. Topics include an in-depth look at the AP Spanish Language and Culture gateway hypothesis and trends in family characteristics such as parent…

  8. Two Successful Approaches to Teaching AP Government

    Science.gov (United States)

    Ladd, Brian; Stepp, Heidi

    2013-01-01

    Amador Valley High School, in Pleasanton, California, uses two unique approaches to teaching Advanced Placement Government and Politics. AP Government consists of six units: Constitutional Underpinnings; Political Behavior and Political Beliefs; Mass Media, Interest Groups, and Political Parties; Institutions of Government; Civil Liberties and…

  9. Confirmatory analysis of the AP1000 passive residual heat removal heat exchanger with 3-D computational fluid dynamic analysis

    International Nuclear Information System (INIS)

    The AP1000 is an 1100 MWe advanced nuclear power plant that uses passive safety features to enhance plant safety and to provide significant and measurable improvements in plant simplification, reliability, investment protection and plant costs. The AP1000 received final design approval from the US-NRC in 2004. The AP1000 design is based on the AP600 design that received final design approval in 1999. Wherever possible, the AP1000 plant configuration and layout was kept the same as AP600 to take advantage of the maturity of the design and to minimize new design efforts. As a result, the two-loop configuration was maintained for AP1000, and the containment vessel diameter was kept the same. It was determined that this significant power up-rate was well within the capability of the passive safety features, and that the safety margins for AP1000 were greater than those of operating PWRs. A key feature of the passive core cooling system is the passive residual heat removal heat exchanger (PRHR HX) that provides decay heat removal for postulated LOCA and non-LOCA events. The PRHR HX is a C-tube heat exchanger located in the in-containment refueling water storage tank (IRWST) above the core promoting natural circulation heat removal between the reactor cooling system and the tank. Component testing was performed for the AP600 PRHR HX to determine the heat transfer characteristics and to develop correlations to be used for the AP1000 safety analysis codes. The data from these tests were confirmed by subsequent integral tests at three separate facilities including the ROSA facility in Japan. Owing to the importance of this component, an independent analysis has been performed using the ATHOS-based computational fluid dynamics computer code PRHRCFD. Two separate models of the PRHR HX and IRWST have been developed representing the ROSA test geometry and the AP1000 plant geometry. Confirmation of the ROSA test results were used to validate PRHRCFD, and the AP1000 plant model

  10. Tank 241-AP-106, grab samples, 6AP-96-1 through 6AP-96-3 analytical results for the final report

    Energy Technology Data Exchange (ETDEWEB)

    Esch, R.A., Westinghouse Hanford

    1996-12-11

    This document is the final report for tank 241-AP-106 grab samples. This document presents the analytical results for three samples (6AP-96-1, 6AP-96-2 and 6AP-96-3) taken from riser 1 @ 150{degrees} of tank 241-AP-1 06 on September 12, 1996. Analyses were performed in accordance with the Compatibility Grab Sampling and Analysis Plan (TSAP) (Sasaki, 1996) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) (Fowler, 1995).

  11. The Clathrin Adaptor AP-1A Mediates Basolateral Polarity

    OpenAIRE

    Gravotta, Diego; Carvajal-Gonzalez, Jose Maria; Mattera, Rafael; Deborde, Sylvie; Banfelder, Jason R.; Bonifacino, Juan S.; Rodriguez-Boulan, Enrique

    2012-01-01

    Clathrin and the epithelial-specific clathrin adaptor AP-1B mediate basolateral trafficking in epithelia. However, several epithelia lack AP-1B and mice knocked-out for AP-1B are viable, suggesting the existence of additional mechanisms that control basolateral polarity. Here, we demonstrate a distinct role of the ubiquitous clathrin adaptor AP-1A in basolateral protein sorting. Knock-down of AP-1A causes missorting of basolateral proteins in MDCK cells but only after knock-down of AP-1B, sug...

  12. Design of the AP 600 passive containment cooling system structures

    International Nuclear Information System (INIS)

    The AP 600 is a greatly simplified 600 MWe Pressurized Water Reactor, for the 1990's and beyond. Among its major features, a passive containment cooling system (PCCS) is designed to remove the residual heat, directly from the containment steel vessel, and transmits it to the environment. The design and analysis of the PCCS structures is being performed jointly by ANSALDO and WESTINGHOUSE, as part of the AP 600 program under WESTINGHOUSE's overall leadership, and will be presented in this paper. The PCCS uses the steel containment wall as a heat transfer surface. The surrounding concrete shield building is used along with a baffle to direct air from the top located air inlets down to a lower elevation of the containment and back up along the containment vessel. In addition a water storage tank is housed in the shield building roof at an elevation sufficient to allow gravity drain of the water on top of the steel containment. The air and the evaporated water exhaust through a chimney in the roof of the shield building. For the roof, a reinforced concrete conical configuration, with a cylindrical stainless steel lined water tank, has been selected and a comprehensive feasibility study has been performed including seismic behaviour, constructability, prefabrication and modularization, adaptability to cope with the External Events strength requirements. For the PCCS air baffles general functional and structural design criteria have been established by including requirements for the air flow path configuration, leaded through the baffles, inspection and maintenance; a series of alternate designs have analyzed, leading to the selection of a reference configuration that will be briefly described. (author). 11 fig

  13. Dynamics of intracellular clathrin/AP1 and clathrin/AP3 containing carriers

    OpenAIRE

    2012-01-01

    Clathrin/AP1 and clathrin/AP3 coated vesicular carriers originate from endosomes and the TGN. We report here the real-time visualization of these structures in living cells reliably tracked by using rapid, three-dimensional imaging with a spinning-disk confocal microscope. We imaged relatively sparse, diffraction-limited, fluorescent objects containing chimeric fluorescent protein (clathrin light chain, σ adaptor subunits or dynamin2) with a spatial precision of up to ~ 30 nm and a temporal r...

  14. Comparative analysis between radiographic views for knee osteoarthrosis (bipedal AP versus monopedal AP

    Directory of Open Access Journals (Sweden)

    Rodrigo Pires e Albuquerque

    2013-08-01

    Full Text Available OBJECTIVE: A comparative analysis by applying the criteria of the original classification Ahlbäck in the anteroposterior (AP bipedal knee in extension and anteroposterior (AP monopodal knee in symptomatic knee arthrosis. With this analysis we intend to observe the agreement, any advantage or difference between the incidence and degree of joint involvement between the orthopedic surgeons and radiologists with the referring physician. METHODS: From January 2012 to March 2012, was a prospective study of 60 symptomatic arthrosis knees (60 patients, clinically selected group of outpatient knee and radiographic proposals submitted to the search. Of the 60 patients, 39 were female and 21 male, mean age 64 years (ranging from 50 to 84 years. Of the 60 knees studied, 37 corresponded to the right side and 23 on the left side. Statistical analysis was performed by Kappa statistics, which evaluates the interobserver agreement for qualitative data. RESULTS: According to the scale of Ahlbäck, there was a significant agreement (p < 0.0001 intra-observer in the classification of knee osteoarthritis among the five evaluators. There was a significant agreement (p < 0.0001 with inter-observer referring physician in the incidence of AP monopodal and AP bipedal for the four raters. CONCLUSION: The study found no difference between the incidence in the AP monopodal versus AP bipedal in osteoarthritis of the knee.

  15. The next generation of power reactors - safety characteristics

    International Nuclear Information System (INIS)

    The next generation of commercial nuclear power reactors is characterized by a new approach to achieving reliability of their safety systems. In contrast to current generation reactors, these designs apply passive safety features that rely on gravity-driven transfer processes or stored energy, such as gas-pressurized accumulators or electric batteries. This paper discusses the passive safety system of the AP600 and Simplified Boiling Water Reactor (SBWR) designs

  16. Characterization of liquid entrainment in the AP1000 automatic depressurization system from APEX tests

    International Nuclear Information System (INIS)

    Full text of publication follows: The AP1000 is a 1000 MWe advanced nuclear power plant that uses passive safety features to enhance plant safety and to provide significant and measurable improvements in plant simplification, reliability, investment protection and plant costs. The AP1000 relies heavily on the 600 MWe AP600 which received design certification in 1999. A critical part of the AP600 design certification process involved the testing of the passive safety systems. A one-fourth height, one-fourth pressure test facility, APEX-600, was constructed at the Oregon State University to study design basis events, and to provide a body of data to be used to validate the computer models used to analyze the AP600. This facility was extensively modified to reflect the design changes for AP1000 including higher power in the electrically heated rods representing the reactor core, and changes in the size of the pressurizer, core makeup tanks and automatic depressurization system. The APEX-1000 test facility was used to perform design basis accident simulations and separate effects tests to support the AP1000 design certification process. In the event of a LOCA, the AP1000 passive core cooling system provides sources of core makeup water along with an automatic depressurization system (ADS) consisting of several stages of valves which reduce the reactor coolant system pressure in a controlled manner. The final stage of this system, ADS-4, consists of four large valves that open off the hot legs, reducing the pressure to allow gravity injection from the in-containment refueling water storage tank (IRWST) and eventually the containment sump. The 67% increase in power from AP600 to AP1000 results in proportionally larger steam velocities exiting the core. Higher steam velocities could increases the potential for significant liquid entrainment out the ADS-4 lines, affecting the liquid inventory in the reactor. Tests were performed in APEX-1000 to characterize the two

  17. Characterization of liquid entrainment in the AP1000 automatic depressurization system from APEX tests

    Energy Technology Data Exchange (ETDEWEB)

    Richard F Wright; Terry L Schulz [Westinghouse Electric Co., PO Box 355, Pittsburgh, PA (United States); Jose N Reyes; John Groome [Oregon State University, Corvallis, OR (United States)

    2005-07-01

    Full text of publication follows: The AP1000 is a 1000 MWe advanced nuclear power plant that uses passive safety features to enhance plant safety and to provide significant and measurable improvements in plant simplification, reliability, investment protection and plant costs. The AP1000 relies heavily on the 600 MWe AP600 which received design certification in 1999. A critical part of the AP600 design certification process involved the testing of the passive safety systems. A one-fourth height, one-fourth pressure test facility, APEX-600, was constructed at the Oregon State University to study design basis events, and to provide a body of data to be used to validate the computer models used to analyze the AP600. This facility was extensively modified to reflect the design changes for AP1000 including higher power in the electrically heated rods representing the reactor core, and changes in the size of the pressurizer, core makeup tanks and automatic depressurization system. The APEX-1000 test facility was used to perform design basis accident simulations and separate effects tests to support the AP1000 design certification process. In the event of a LOCA, the AP1000 passive core cooling system provides sources of core makeup water along with an automatic depressurization system (ADS) consisting of several stages of valves which reduce the reactor coolant system pressure in a controlled manner. The final stage of this system, ADS-4, consists of four large valves that open off the hot legs, reducing the pressure to allow gravity injection from the in-containment refueling water storage tank (IRWST) and eventually the containment sump. The 67% increase in power from AP600 to AP1000 results in proportionally larger steam velocities exiting the core. Higher steam velocities could increases the potential for significant liquid entrainment out the ADS-4 lines, affecting the liquid inventory in the reactor. Tests were performed in APEX-1000 to characterize the two

  18. AP1000R design robustness against extreme external events - Seismic, flooding, and aircraft crash

    International Nuclear Information System (INIS)

    Both the International Atomic Energy Agency (IAEA) and the U.S. Nuclear Regulatory Commission (NRC) require existing and new nuclear power plants to conduct plant assessments to demonstrate the unit's ability to withstand external hazards. The events that occurred at the Fukushima-Dai-ichi nuclear power station demonstrated the importance of designing a nuclear power plant with the ability to protect the plant against extreme external hazards. The innovative design of the AP1000R nuclear power plant provides unparalleled protection against catastrophic external events which can lead to extensive infrastructure damage and place the plant in an extended abnormal situation. The AP1000 plant is an 1100-MWe pressurized water reactor with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance and safety. The plant's compact safety related footprint and protection provided by its robust nuclear island structures prevent significant damage to systems, structures, and components required to safely shutdown the plant and maintain core and spent fuel pool cooling and containment integrity following extreme external events. The AP1000 nuclear power plant has been extensively analyzed and reviewed to demonstrate that it's nuclear island design and plant layout provide protection against both design basis and extreme beyond design basis external hazards such as extreme seismic events, external flooding that exceeds the maximum probable flood limit, and malicious aircraft impact. The AP1000 nuclear power plant uses fail safe passive features to mitigate design basis accidents. The passive safety systems are designed to function without safety-grade support systems (such as AC power, component cooling water, service water, compressed air or HVAC). The plant has been designed to protect systems, structures, and components critical to placing the reactor in a safe shutdown condition within the steel containment vessel which is

  19. The AP-1A and AP-1B clathrin adaptor complexes define biochemically and functionally distinct membrane domains

    OpenAIRE

    Fölsch, Heike; Pypaert, Marc; Maday, Sandra; Pelletier, Laurence; Mellman, Ira

    2003-01-01

    Most epithelial cells contain two AP-1 clathrin adaptor complexes. AP-1A is ubiquitously expressed and involved in transport between the TGN and endosomes. AP-1B is expressed only in epithelia and mediates the polarized targeting of membrane proteins to the basolateral surface. Both AP-1 complexes are heterotetramers and differ only in their 50-kD μ1A or μ1B subunits. Here, we show that AP-1A and AP-1B, together with their respective cargoes, define physically and functionally distinct membra...

  20. Potential for AP600 in-vessel retention through ex-vessel flooding

    Energy Technology Data Exchange (ETDEWEB)

    Rempe, J.L.; Knudson, D.L.; Allison, C.M.; Thinnes, G.L.; Atwood, C.L.

    1997-12-01

    External reactor vessel cooling (ERVC) is a new severe accident management strategy that involves flooding the reactor cavity to submerge the reactor vessel in an attempt to cool core debris that has relocated to the vessel lower head. Advanced and existing light water reactors (LWRs) are considering ERVC as an accident management strategy for in-vessel retention (IVR) of relocated debris. In the probabilistic risk assessment (PRA) for the AP600 design, Westinghouse credits ERVC for preventing vessel failure during postulated severe accidents with successful reactor coolant system (RCS) depressurization and reactor cavity flooding. To support the Westinghouse position on IVR, DOE contracted the University of California--Santa Barbara (UCSB) to produce the peer-reviewed report. To assist in the NRC`s evaluation of IVR of core melt by ex-vessel flooding of the AP6OO, the Idaho National Engineering and Environmental Laboratory (INEEL) was tasked to perform: An in-depth critical review of the UCSB study and the model that UCSB used to assess ERVC effectiveness; An in-depth review of the UCSB study peer review comments and of UCSB`s resolution method to identify areas where technical concerns weren`t addressed; and An independent analysis effort to investigate the impact of residual concerns on the margins to failure and conclusions presented in the UCSB study. This report summarizes results from these tasks. As discussed in Sections 1.1 and 1.2, INEEL`s review of the UCSB study and peer reviewer comments suggested that additional analysis was needed to assess: (1) the integral impact of peer reviewer-suggested changes to input assumptions and uncertainties and (2) the challenge present by other credible debris configurations. Section 1.3 summarized the corresponding analysis approach developed by INEEL. The remainder of this report provides more detailed descriptions of analysis methodology, input assumptions, and results.

  1. The design and construction of the AP1000 nuclear power plant - The application of generation III+ technology

    International Nuclear Information System (INIS)

    The evolutionary design of the AP1000 reactor provides several distinct advantages over other designs, including the highest safety and performance standards, economic competitiveness, reduced construction schedule risks, and improved operations. Domestic and foreign utilities have turned to the Westinghouse AP1000 plant design to meet their near- and long-term sustainable energy needs. The AP1000 design reduced the amount of safety-grade equipment required by the application of passive safety systems. These passive systems are sufficient to automatically establish and maintain core cooling and containment integrity indefinitely following design-basis events, assuming the most limiting single failure, with no operator action and no ac power sources. The AP1000 design incorporates modern, modular, engineering principles that allow construction and fabrication tasks, traditionally performed in sequence, to be undertaken in parallel. Structural, piping, and equipment modules provide the benefits of module fabrication in controlled workshop conditions, significantly reducing field construction work scope. The AP1000 design is the only Generation III+ technology to receive design certification from the U.S. Nuclear Regulatory Commission (NRC). Westinghouse AP1000 nuclear power plants are currently being constructed in China (Sanmen and Haiyang sites) and the United States (Vogtle site)

  2. Fuzzy uncertainty modeling applied to AP1000 nuclear power plant LOCA

    International Nuclear Information System (INIS)

    Research highlights: → This article presents an uncertainty modelling study using a fuzzy approach. → The AP1000 Westinghouse NPP was used and it is provided of passive safety systems. → The use of advanced passive safety systems in NPP has limited operational experience. → Failure rates and basic events probabilities used on the fault tree analysis. → Fuzzy uncertainty approach was employed to reliability of the AP1000 large LOCA. - Abstract: This article presents an uncertainty modeling study using a fuzzy approach applied to the Westinghouse advanced nuclear reactor. The AP1000 Westinghouse Nuclear Power Plant (NPP) is provided of passive safety systems, based on thermo physics phenomenon, that require no operating actions, soon after an incident has been detected. The use of advanced passive safety systems in NPP has limited operational experience. As it occurs in any reliability study, statistically non-significant events report introduces a significant uncertainty level about the failure rates and basic events probabilities used on the fault tree analysis (FTA). In order to model this uncertainty, a fuzzy approach was employed to reliability analysis of the AP1000 large break Loss of Coolant Accident (LOCA). The final results have revealed that the proposed approach may be successfully applied to modeling of uncertainties in safety studies.

  3. Reactor Physics

    International Nuclear Information System (INIS)

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised

  4. Reactor Physics

    International Nuclear Information System (INIS)

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised

  5. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2001-04-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised.

  6. Modeliranje nove jedrske elektrarne tipa AP1000

    OpenAIRE

    GERJEVIČ, GREGA

    2015-01-01

    Diplomsko delo zajema primerjavo rezultatov simulacije male izlivne nezgode s programskim orodjem Advanced PWR simulator z rezultati, ki jih je opravilo podjetje Westinghouse v testnem objektu APEX-1000. V prvem delu diplomskega dela sta opisana primarni in sekundarni sistem, ki se bistveno ne razlikujeta od sistemov ostalih jedrskih elektrarn. Nato sledi opis pasivnih varnostnih sistemov, po katerih je AP1000 znana. Sledi splošen opis izlivne nezgode, simulacijskega orodja in potek simul...

  7. Magnetic Doppler Imaging of Ap stars

    OpenAIRE

    Silvester, J.; Wade, G. A.; Kochukhov, O.; Landstreet, J. D.; Bagnulo, S.

    2007-01-01

    Historically, the magnetic field geometries of the chemically peculiar Ap stars were modelled in the context of a simple dipole field. However, with the acquisition of increasingly sophisticated diagnostic data, it has become clear that the large-scale field topologies exhibit important departures from this simple model. Recently, new high-resolution circular and linear polarisation spectroscopy has even hinted at the presence of strong, small-scale field structures, which were completely une...

  8. Final report for tank 241-AP-108, grab samples 8AP-96-1, 8AP-96-2 and 8AP-96-FB

    International Nuclear Information System (INIS)

    This document is the final report deliverable for the tank 241-AP-108 grab samples. The samples were subsampled and analyzed in accordance with the TSAP. Included in this report are the results for the Waste Compatibility analyses, with the exception of DSC and thermogravimetric analysis (TGA) results which were presented in the 45 Day report (Part 2 of this document). The raw data for all analyses, with the exception of DSC and TGA, are also included in this report

  9. APS storage ring vacuum system performance

    International Nuclear Information System (INIS)

    The Advanced Photon Source (APS) storage ring was designed to operated with 7-GeV, 100-mA positron beam with lifetimes > 20 hours. The lifetime is limited by residual gas scattering and Touschek scattering at this time. Photon-stimulated desorption and microwave power in the rf cavities are the main gas loads. Comparison of actual system gas loads and design calculations will be given. In addition, several special features of the storage ring vacuum system will be presented

  10. AP-42 ADDITIONS AND REVISIONS - RESIDENTIAL WOOD COMBUSTION

    Science.gov (United States)

    This project develops emission factors, etc., for residential fireplaces and woodstoves which are incorporated into AP-42. AP42 is a massive collection of material which describes processes which generate air emissions and presents emission factors and control effectiveness infor...

  11. Dicty_cDB: FC-AP07 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available FC (Link to library) FC-AP07 (Link to dictyBase) - - - Contig-U15932-1 FC-AP07P (Li...nk to Original site) FC-AP07F 546 FC-AP07Z 446 FC-AP07P 992 - - Show FC-AP07 Library FC (Link to library) Clone ID FC-AP...al site URL http://dictycdb.biol.tsukuba.ac.jp/CSM/FC/FC-AP/FC-AP07Q.Seq.d/ Representative seq. ID FC-AP...07P (Link to Original site) Representative DNA sequence >FC-AP07 (FC-AP07Q) /CSM/FC/FC-AP/FC-AP...ificant alignments: (bits) Value FC-AP07 (FC-AP07Q) /CSM/FC/FC-AP/FC-AP07Q.Seq.d/ 1148 0.0 SSM404 (SSM404Q)

  12. Dicty_cDB: FC-AP08 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available FC (Link to library) FC-AP08 (Link to dictyBase) - - - Contig-U16116-1 FC-AP08P (Li...nk to Original site) FC-AP08F 125 FC-AP08Z 352 FC-AP08P 477 - - Show FC-AP08 Library FC (Link to library) Clone ID FC-AP...al site URL http://dictycdb.biol.tsukuba.ac.jp/CSM/FC/FC-AP/FC-AP08Q.Seq.d/ Representative seq. ID FC-AP...08P (Link to Original site) Representative DNA sequence >FC-AP08 (FC-AP08Q) /CSM/FC/FC-AP/FC-AP... (VSA612Q) /CSM/VS/VSA6-A/VSA612Q.Seq.d/ 624 e-178 FC-AP08 (FC-AP08Q) /CSM/FC/FC-AP/FC-AP

  13. Reactor operation

    CERN Document Server

    Shaw, J

    2013-01-01

    Reactor Operation covers the theoretical aspects and design information of nuclear reactors. This book is composed of nine chapters that also consider their control, calibration, and experimentation.The opening chapters present the general problems of reactor operation and the principles of reactor control and operation. The succeeding chapters deal with the instrumentation, start-up, pre-commissioning, and physical experiments of nuclear reactors. The remaining chapters are devoted to the control rod calibrations and temperature coefficient measurements in the reactor. These chapters also exp

  14. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    2013-01-01

    Reactor Safeguards provides information for all who are interested in the subject of reactor safeguards. Much of the material is descriptive although some sections are written for the engineer or physicist directly concerned with hazards analysis or site selection problems. The book opens with an introductory chapter on radiation hazards, the construction of nuclear reactors, safety issues, and the operation of nuclear reactors. This is followed by separate chapters that discuss radioactive materials, reactor kinetics, control and safety systems, containment, safety features for water reactor

  15. AP Deployment Research Based on Physical Distance and Channel Isolation

    OpenAIRE

    Dangui Yan; Chengchang Zhang; Honghua Liao; Lisheng Yang; Ping Li; Guogang Yang

    2014-01-01

    Aiming at the problem of inefficiency of wireless local area networks (WLAN) access point (AP) deployment in urban environment, a new algorithm for AP deployment based on physical distance and channel isolation (DPDCI) is proposed. First, it detects the position information of deployed APs and then calculates the interference penalty factor combined with physical distance and channel isolation, and finally gets the optimal location and channel of the new AP through the genetic algorithm. Comp...

  16. AIRE variations in Addison's disease and autoimmune polyendocrine syndromes (APS)

    DEFF Research Database (Denmark)

    Bøe Wolff, A S; Oftedal, B; Johansson, S; Bruland, O; Løvås, K; Meager, A; Pedersen, Carsten; Husebye, E S; Knappskog, P M

    2008-01-01

    Autoimmune Addison's disease (AAD) is often associated with other components in autoimmune polyendocrine syndromes (APS). Whereas APS I is caused by mutations in the AIRE gene, the susceptibility genes for AAD and APS II are unclear. In the present study, we investigated whether polymorphisms or...

  17. Evaluation of the Scaling of the APEX-1000 Test Facility to AP1000 for Design Basis Events

    International Nuclear Information System (INIS)

    The AP1000 is a 1000 MWe advanced nuclear power plant that uses passive safety features to enhance plant safety and to provide significant and measurable improvements in plant simplification, reliability, investment protection and plant costs. The AP1000 relies heavily on the 600 MWe AP600 which received design certification in 1999. A critical part of the AP600 design certification process involved the testing of the passive safety systems. A one-fourth height, one-fourth pressure test facility, APEX-600, was constructed at the Oregon State University to study design basis events, and to provide a body of data to be used to validate the computer models used to analyze the AP600. This facility was extensively modified to reflect the design changes for AP1000 including higher power in the electrically heated rods representing the reactor core, and changes in the size of the pressurizer, core makeup tanks and automatic depressurization system. Several design basis events have been simulated at APEX-1000 including double-ended direct vessel injection (DEDVI) line break, 2-inch cold leg break, and inadvertent actuation of the automatic depressurization system. These events were analyzed as part of the AP1000 safety analysis using the NOTRUMP computer code. Applying the scaling factors that were used to size the APEX-1000 facility, the test results can be compared to the NOTRUMP plant simulations. These comparisons indicate the similarity between the design basis events in AP1000 and APEX-1000, the adequacy of the scaling of APEX-1000, and the applicability of the NOTRUMP code. (authors)

  18. Addressing the fundamental issues in reliability evaluation of passive safety of AP1000 for a comparison with active safety of PWR

    International Nuclear Information System (INIS)

    Passive safety systems adopted in advanced Pressurized Water Reactor (PWR), such as AP1000 and EPR, should attain higher reliability than the existing active safety systems of the conventional PWR. The objective of this study is to discuss the fundamental issues relating to the reliability evaluation of AP1000 passive safety systems for a comparison with the active safety systems of conventional PWR, based on several aspects. First, comparisons between conventional PWR and AP1000 are made from the both aspects of safety design and cost reduction. The main differences between these PWR plants exist in the configurations of safety systems: AP1000 employs the passive safety system while reducing the number of active systems. Second, the safety of AP1000 is discussed from the aspect of severe accident prevention in the event of large break loss of coolant accidents (LOCA). Third, detailed fundamental issues on reliability evaluation of AP1000 passive safety systems are discussed qualitatively by using single loop models of safety systems of both PWRs plants. Lastly, methodology to conduct quantitative estimation of dynamic reliability for AP1000 passive safety systems in LOCA condition is discussed, in order to evaluate the reliability of AP1000 in future by a success-path-based reliability analysis method (i.e., GO-FLOW). (author)

  19. AP1000 plant pressurizer overfilling prevention study against station blackout accident

    International Nuclear Information System (INIS)

    If loss of main feed-water occurs in a station blackout accident for AP1000 plant, the pressurizer will overfill and the coolant will be discharged through pressurizer safety valves. It results in a loss of coolant accident, RCS inventory will decrease, and the risk of reactor core uncovering increases. Because of the coolant discharging, the atmosphere radiation level in the containment may be raised, while the possibility of radioactive release to the environment increases. In order to prevent pressurizer overfilling, an effective strategy to avoid and mitigate pressurizer overfilling was provided. The results show that increasing heat transfer areas of PRHRS heat exchanger can prevent pressurizer overfilling; reasonable decreasing of IRWST back pressure can enhance mar gins of pressurizer overfilling, and mitigate pressurizer overfilling phenomena; increasing pressurizer volumes can also avoid pressurizer overfilling. The conclusions have reference value in helping design and safety analysis of AP1000 plant. (authors)

  20. Analysis of large release source terms in AP1000 nuclear power plant

    International Nuclear Information System (INIS)

    In some severe accident scenarios of AP1000 nuclear power plant, a breach or bypass of the containment will lead to large release to environment, which causes severe radioactive pollution of environment. Three release categories (bypass, early containment failure and containment isolation failure) have the largest contribution to large release frequency. Three typical severe accidents (steam generator tube rupture, spuriously open of automatic depressurization system valves and reactor pressure vessel rupture) were selected as typical cases corresponding to the three release categories and the fission-product source terms released to environment were calculated using MAAP code. The analysis results are provided as essential input data for quantifying the release of AP1000 nuclear power plant and the offsite dose analysis. (author)

  1. Dicty_cDB: FC-AP01 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available FC (Link to library) FC-AP01 (Link to dictyBase) - - - Contig-U15092-1 FC-AP01Z (Li...nk to Original site) - - FC-AP01Z 591 - - - - Show FC-AP01 Library FC (Link to library) Clone ID FC-AP01 (Li.../dictycdb.biol.tsukuba.ac.jp/CSM/FC/FC-AP/FC-AP01Q.Seq.d/ Representative seq. ID FC-AP...01Z (Link to Original site) Representative DNA sequence >FC-AP01 (FC-AP01Q) /CSM/FC/FC-AP/FC-AP01Q.Seq....EELNISGPLSRNKLKWADFLNLTMNTNHARG HRHGRSPSKIFWRAVRGMLPHKTPRGQAALDNMKVFEGVPAPYDKVKRVVVPSALRVVKL NTTRKYTVLSRLSQE

  2. Dicty_cDB: FC-AP10 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available FC (Link to library) FC-AP10 (Link to dictyBase) - - - Contig-U15819-1 FC-AP10Z (Li...nk to Original site) - - FC-AP10Z 497 - - - - Show FC-AP10 Library FC (Link to library) Clone ID FC-AP10 (Li.../dictycdb.biol.tsukuba.ac.jp/CSM/FC/FC-AP/FC-AP10Q.Seq.d/ Representative seq. ID FC-AP...10Z (Link to Original site) Representative DNA sequence >FC-AP10 (FC-AP10Q) /CSM/FC/FC-AP/FC-AP10Q.Seq....SGDWWDAELKGRRGKVPSNYLQLIKNAAPPRAGGPPVPTGNRA PTTTTTSGGSTRGGFNNGPSTAPSGRGAAPPSSRGGMAPRGGSVAPPSSRGGIAPRGGIA PRGGMAPRGGMAP

  3. Pharmakologische Charakterisierung der vasoaktiven Eigenschaften von Ap7A und Ap8A an der isolierten perfundierten Rattenniere

    OpenAIRE

    Blaschke, Daniela

    2010-01-01

    Recently, diadenosine heptaphosphate and diadenosine octaphosphate have been isolated in human platelets. With thrombin-induced platelet aggregation, Ap7A and Ap8A are released from the platelets into the extracellular space. Like other dinucleoside polyphosphates, maybe they play an important role in the control of vascular tone and platelet aggregation. Here we describe the effects on regulation of vascular tone of Ap7A and Ap8A in isolated perfused rat kidney. Our experiments demonstrate t...

  4. Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Martens, Frederick H. [Argonne National Laboratory; Jacobson, Norman H.

    1968-09-01

    This booklet discusses research reactors - reactors designed to provide a source of neutrons and/or gamma radiation for research, or to aid in the investigation of the effects of radiation on any type of material.

  5. 77 FR 24480 - Application for New Awards; Advanced Placement (AP) Test Fee Program-Reopening the AP Test Fee...

    Science.gov (United States)

    2012-04-24

    .... ACTION: Notice reopening the AP Test Fee fiscal year 2012 competition. Catalog of Federal Domestic Assistance (CFDA) Number: 84.330B. SUMMARY: On February 15, 2012, we published in the Federal Register (77 FR... Application for New Awards; Advanced Placement (AP) Test Fee Program--Reopening the AP Test Fee Fiscal...

  6. Research reactors

    International Nuclear Information System (INIS)

    This article proposes an overview of research reactors, i.e. nuclear reactors of less than 100 MW. Generally, these reactors are used as neutron generators for basic research in matter sciences and for technological research as a support to power reactors. The author proposes an overview of the general design of research reactors in terms of core size, of number of fissions, of neutron flow, of neutron space distribution. He outlines that this design is a compromise between a compact enough core, a sufficient experiment volume, and high enough power densities without affecting neutron performance or its experimental use. The author evokes the safety framework (same regulations as for power reactors, more constraining measures after Fukushima, international bodies). He presents the main characteristics and operation of the two families which represent almost all research reactors; firstly, heavy water reactors (photos, drawings and figures illustrate different examples); and secondly light water moderated and cooled reactors with a distinction between open core pool reactors like Melusine and Triton, pool reactors with containment, experimental fast breeder reactors (Rapsodie, the Russian BOR 60, the Chinese CEFR). The author describes the main uses of research reactors: basic research, applied and technological research, safety tests, production of radio-isotopes for medicine and industry, analysis of elements present under the form of traces at very low concentrations, non destructive testing, doping of silicon mono-crystalline ingots. The author then discusses the relationship between research reactors and non proliferation, and finally evokes perspectives (decrease of the number of research reactors in the world, the Jules Horowitz project)

  7. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    Mathematical methods and computer calculations for nuclear and thermonuclear reactor kinetics, reactor physics, neutron transport theory, core lattice parameters, waste treatment by transmutation, breeding, nuclear and thermonuclear fuels are the main interests of the conference

  8. Research reactors

    International Nuclear Information System (INIS)

    There are currently 284 research reactors in operation, and 12 under construction around the world. Of the operating reactors, nearly two-thirds are used exclusively for research, and the rest for a variety of purposes, including training, testing, and critical assembly. For more than 50 years, research reactor programs have contributed greatly to the scientific and educational communities. Today, six of the world's research reactors are being shut down, three of which are in the USA. With government budget constraints and the growing proliferation concerns surrounding the use of highly enriched uranium in some of these reactors, the future of nuclear research could be impacted

  9. Reactor container

    International Nuclear Information System (INIS)

    Object: To provide a jet and missile protective wall of a configuration being inflated toward the center of a reactor container on the inside of a body of the reactor container disposed within a biological shield wall to thereby increase safety of the reactor container. Structure: A jet and missile protective wall comprised of curved surfaces internally formed with a plurality of arch inflations filled with concrete between inner and outer iron plates and shape steel beam is provided between a reactor container surrounded by a biological shield wall and a thermal shield wall surrounding the reactor pressure vessel, and an adiabatic heat insulating material is filled in space therebetween. (Yoshino, Y.)

  10. Ozone mitigation tests at the APS

    International Nuclear Information System (INIS)

    Ozone is generated in the APS experimental stations whenever the x-ray beam has a chance to interact with air. Ozone concentrations in an experimental station have to be below a certain defined limit (current OSHA regulations specify 0.08 ppm as the maximum limit) before an experimenter can reenter the hutch. This limit is said to be currently under study for a downward adjustment. One method of depleting the ozone generated in an experimental station is mitigation through either adsorption or direct destruction. In recent tests, both methods were tried using commercially available units. Test results and some analytical predictions are presented

  11. Wiley AP english language and composition

    CERN Document Server

    Woods, Geraldine

    2013-01-01

    Two full-length practice tests to help you score your highest Review questions with complete answers and explanations for the most popular themes on the test Study strategies and expert test-taking tips to keep you calm and focused on test day Review key exam topics and themes to maximize your score Preparing for the AP English Language and Composition test? This test-prep guide helps you perfect the skills you need to achieve your best possible score. You'll find winning test-taking tips, multiple-choice strategies, and essay guidelines, as well as great advice on getting the

  12. Dicty_cDB: FC-AP24 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available FC (Link to library) FC-AP24 (Link to dictyBase) - - - Contig-U16528-1 FC-AP24F (Li...nk to Original site) FC-AP24F 525 - - - - - - Show FC-AP24 Library FC (Link to library) Clone ID FC-AP24 (Li.../dictycdb.biol.tsukuba.ac.jp/CSM/FC/FC-AP/FC-AP24Q.Seq.d/ Representative seq. ID FC-AP...24F (Link to Original site) Representative DNA sequence >FC-AP24 (FC-AP24Q) /CSM/FC/FC-AP/FC-AP24Q.Seq....C-BE24Q.Seq.d/ 1041 0.0 FC-AP24 (FC-AP24Q) /CSM/FC/FC-AP/FC-AP24Q.Seq.d/ 1041 0.0

  13. Dicty_cDB: FC-AP21 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available FC (Link to library) FC-AP21 (Link to dictyBase) - - - Contig-U15099-1 FC-AP21Z (Li...nk to Original site) - - FC-AP21Z 511 - - - - Show FC-AP21 Library FC (Link to library) Clone ID FC-AP21 (Li.../dictycdb.biol.tsukuba.ac.jp/CSM/FC/FC-AP/FC-AP21Q.Seq.d/ Representative seq. ID FC-AP...21Z (Link to Original site) Representative DNA sequence >FC-AP21 (FC-AP21Q) /CSM/FC/FC-AP/FC-AP21Q.Seq....14Q.Seq.d/ 1013 0.0 SLE553 (SLE553Q) /CSM/SL/SLE5-C/SLE553Q.Seq.d/ 1013 0.0 FC-AP21 (FC-AP21Q) /CSM/FC/FC-AP/FC-AP

  14. Dicty_cDB: FC-AP22 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available FC (Link to library) FC-AP22 (Link to dictyBase) - G24045 DDB0232387 Contig-U15141-1 FC-AP...22F (Link to Original site) FC-AP22F 317 - - - - - - Show FC-AP22 Library FC (Link to library) Clone ID FC-AP...1-1 Original site URL http://dictycdb.biol.tsukuba.ac.jp/CSM/FC/FC-AP/FC-AP22Q.Se...q.d/ Representative seq. ID FC-AP22F (Link to Original site) Representative DNA sequence >FC-AP22 (FC-AP22Q) /CSM/FC/FC-AP/FC-AP...KKKKKKK Homology vs CSM-cDNA Score E Sequences producing significant alignments: (bits) Value FC-AP22 (FC-AP22Q) /CSM/FC/FC-AP/FC-AP

  15. Correction magnet power supplies for APS machine

    International Nuclear Information System (INIS)

    A number of correction magnets are required for the advanced photon source (APS) machine to correct the beam. There are five kinds of correction magnets for the storage ring, two for the injector synchrotron, and two for the positron accumulator ring (PAR). Table I shoes a summary of the correction magnet power supplies for the APS machine. For the storage ring, the displacement of the quadrupole magnets due to the low frequency vibration below 25 Hz has the most significant effect on the stability of the positron closed orbit. The primary external source of the low frequency vibration is the ground motion of approximately 20 μm amplitude, with frequency components concentrated below 10 Hz. These low frequency vibrations can be corrected by using the correction magnets, whose field strengths are controlled individually through the feedback loop comprising the beam position monitoring system. The correction field require could be either positive or negative. Thus for all the correction magnets, bipolar power supplies (BPSs) are required to produce both polarities of correction fields. Three different types of BPS are used for all the correction magnets. Type I BPSs cover all the correction magnets for the storage ring, except for the trim dipoles. The maximum output current of the Type I BPS is 140 Adc. A Type II BPS powers a trim dipole, and its maximum output current is 60 Adc. The injector synchrotron and PAR correction magnets are powered form Type III BPSs, whose maximum output current is 25 Adc

  16. APS insertion devices: Recent developments and results

    International Nuclear Information System (INIS)

    The Advanced Photon Source (APS) now has a total of 23 insertion devices (IDs). Over two-thirds of them are installed on the storage ring. The installed devices include 18, 27 and 55 mm-period undulators; an 85 mm-period wiggler; a 16 cm-period elliptical multipole wiggler; and many 33 mm-period undulators. Most of the IDs occupy storage-ring straight sections equipped with 8 mm vertical-aperture vacuum chambers. All of the IDs were measured magnetically at the APS and, in most cases, underwent a final magnetic tuning in order to minimize variation in the various integrals of the field through the ID over the full gap range. Special shimming techniques to correct magnetic field parameters in appropriate gap-dependent ways were developed and applied. Measurements of the closed-orbit distortion as a function of the ID gap variation have been completed, and results are in a good agreement with magnetic measurements. Spectral diagnostics of the ID radiation, including measurements of the absolute spectral flux, brilliance and polarization, show excellent agreement between calculated and measured results. Studies of the sensitivity of IDs to radiation exposure and measurements of the dose rate received by the IDs are in progress

  17. The APS control system network upgrade

    International Nuclear Information System (INIS)

    When it was installed,the Advanced Photon Source (APS) control system network was at the state-of-the-art. Different aspects of the system have been reported at previous meetings [1,2]. As loads on the controls network have increased due to newer and faster workstations and front-end computers, we have found performance of the system declining and have implemented an upgraded network. There have been dramatic advances in networking hardware in the last several years. The upgraded APS controls network replaces the original FDDI backbone and shared Ethernet hubs with redundant gigabit uplinks and fully switched 10/100 Ethernet switches with backplane fabrics in excess of 20 Gbits/s (Gbps). The central collapsed backbone FDDI concentrator has been replaced with a Gigabit Ethernet switch with greater than 30 Gbps backplane fabric. Full redundancy of the system has been maintained. This paper will discuss this upgrade and include performance data and performance comparisons with the original network

  18. AP1000R nuclear power plant safety overview for spent fuel cooling

    International Nuclear Information System (INIS)

    The AP1000R plant is an 1100-MWe class pressurized water reactor with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance, safety and costs. The AP1000 design uses passive features to mitigate design basis accidents. The passive safety systems are designed to function without safety-grade support systems such as AC power, component cooling water, service water or HVAC. Furthermore, these passive features 'fail safe' during a non-LOCA event such that DC power and instrumentation are not required. The AP1000 also has simple, active, defense-in-depth systems to support normal plant operations. These active systems provide the first level of defense against more probable events and they provide investment protection, reduce the demands on the passive features and support the probabilistic risk assessment. The AP1000 passive safety approach allows the plant to achieve and maintain safe shutdown in case of an accident for 72 hours without operator action, meeting the expectations provided in the U.S. Utility Requirement Document and the European Utility Requirements for passive plants. Limited operator actions are required to maintain safe conditions in the spent fuel pool via passive means. In line with the AP1000 approach to safety described above, the AP1000 plant design features multiple, diverse lines of defense to ensure spent fuel cooling can be maintained for design-basis events and beyond design-basis accidents. During normal and abnormal conditions, defense-in-depth and other systems provide highly reliable spent fuel pool cooling. They rely on off-site AC power or the on-site standby diesel generators. For unlikely design basis events with an extended loss of AC power (i.e., station blackout) or loss of heat sink or both, spent fuel cooling can still be provided indefinitely: - Passive systems, requiring minimal or no operator actions, are sufficient for at least 72 hours under all possible pool heat

  19. AP1000{sup R} nuclear power plant safety overview for spent fuel cooling

    Energy Technology Data Exchange (ETDEWEB)

    Gorgemans, J.; Mulhollem, L.; Glavin, J.; Pfister, A.; Conway, L.; Schulz, T.; Oriani, L.; Cummins, E.; Winters, J. [Westinghouse Electric Company LLC, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

    2012-07-01

    The AP1000{sup R} plant is an 1100-MWe class pressurized water reactor with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance, safety and costs. The AP1000 design uses passive features to mitigate design basis accidents. The passive safety systems are designed to function without safety-grade support systems such as AC power, component cooling water, service water or HVAC. Furthermore, these passive features 'fail safe' during a non-LOCA event such that DC power and instrumentation are not required. The AP1000 also has simple, active, defense-in-depth systems to support normal plant operations. These active systems provide the first level of defense against more probable events and they provide investment protection, reduce the demands on the passive features and support the probabilistic risk assessment. The AP1000 passive safety approach allows the plant to achieve and maintain safe shutdown in case of an accident for 72 hours without operator action, meeting the expectations provided in the U.S. Utility Requirement Document and the European Utility Requirements for passive plants. Limited operator actions are required to maintain safe conditions in the spent fuel pool via passive means. In line with the AP1000 approach to safety described above, the AP1000 plant design features multiple, diverse lines of defense to ensure spent fuel cooling can be maintained for design-basis events and beyond design-basis accidents. During normal and abnormal conditions, defense-in-depth and other systems provide highly reliable spent fuel pool cooling. They rely on off-site AC power or the on-site standby diesel generators. For unlikely design basis events with an extended loss of AC power (i.e., station blackout) or loss of heat sink or both, spent fuel cooling can still be provided indefinitely: - Passive systems, requiring minimal or no operator actions, are sufficient for at least 72 hours under all

  20. Evaluating EPA’s AP-42 development methodology to convert or rerate current AP-42 datasets

    Science.gov (United States)

    In August 2013, the U.S. Environmental Protection Agency’s (EPA) published their new methodology for updating the Compilation of Air Pollution Emission Factors (AP-42). The “Recommended Procedures for Development of Emissions Factors and Use of the WebFIRE Database” instructs that the ratings of the...

  1. An overview of third generation reactors - Presentation

    International Nuclear Information System (INIS)

    Now, in 2013 about 69 nuclear reactors (67 GWe) are being built in the world, mostly in China and Russia. Although a few second generation reactors are being built (particularly in China), third generation reactors seem to be systematically chosen for any new construction. The French commercial offer is based on 3 models: the EPR, the ATMEA-1 and the KERENA, the first 2 being of PWR-type while the latter is a BWR. A lot of third generation reactor designs are available on the international market. Concerning the PWR technology we have: the EPR (AREVA), the AP1000 (Westinghouse), the AES 2006 and the VVER TOI (Rosatom), the APR1400 (KEPCO), the APWR (MHI), the ATMEA-1 (AREVA + MHI), the ACP 1000 (CNNC - China), ACPR1000 (CGN - China) and CAP 1400 (SNPTC - China). Concerning the BWR technology, the commercial offer is far less important we have: the ABWR (GE-Hitachi + Toshiba) and the ESBWR (GE-Hitachi). Some third generation reactors are operating now: the first ABWR and AES reactors but most of them (EPR, AP1000, APR1400 and AES 2006) are at an advanced stage of construction. (A.C.)

  2. Neutronic and thermal-hydraulic calculations for the AP-1000 NPP with the MCNP6 and SERPENT codes

    Energy Technology Data Exchange (ETDEWEB)

    Stefani, Giovanni Laranjo; Maiorino, Jose R.; Santos, Thiago A., E-mail: giovanni.laranjo@ufabc.edu.br, E-mail: joserubens.maiorino@ufabc.edu.br, E-mail: thiago.santos@ufabc.edu.br [Universidade Federal do ABC (CECS/UFABC), Santo Andre, SP (Brazil). Centro de Engenharia, Modelagem e Ciencias Sociais; Rossi, Pedro R., E-mail: pedro.russorossi@gmail.com [FERMIUM - Tecnologia Nuclear, Sao Paulo, SP (Brazil)

    2015-07-01

    The AP-1000 is an evolutionary PWR reactor designed as an evolution of the AP-600 project. The reactor is already pre-licensed by NRC, and is considered to have achieved high standards of safety, possible short construction time and good economic competitiveness. The core is a 17x17 typical assembly using Zirlo as cladding, 3 different enrichment regions, and is controlled by boron, control banks, and burnable poison. The expected fuel final burnup is 62 MWD/ton U and a cycle of 18 months. In this paper we present results for neutronic and thermal-hydraulic calculations for the AP-1000. We use the MCNP6 and SERPENT codes to calculate the first cycle of operation. The calculated parameters are K{sub eff} at BOL and EOL and its variation with burnup and neutron flux, and reactivity coefficients. The production of transuranic elements such as Pu-239 and Pu-241, and burning fuel are calculated over time. In the work a complete reactor was burned for 450 days with no control elements, boron or burnable poison were considered, these results were compared with data provided by the Westinghouse. The results are compared with those reported in the literature. A simple thermal hydraulic analysis allows verification of thermal limits such as fuel and cladding temperatures, and MDNB. (author)

  3. 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

  4. Radioactive wastes from possible future UK Light Water Reactors

    International Nuclear Information System (INIS)

    The predictive radioactive wastes from the operation and decommissioning of various designs of Light Water Reactor (LWR) are reviewed and compared to the Sizewell 'B' Pressurised Water Reactor. The designs considered are the N4, Konvoi, System 80+, Advanced PWR, AP600, Advanced Boiling Water Reactor, the European Pressurised Water Reactor (EPR) and the Sizewell 'XL' design. The sources of activity, active arisings, waste treatment plants, discharges to the environment, the optimisation of waste treatment, lifetime arisings of solid waste and the characteristics of spent fuel are addressed. Conclusions are drawn on the implications for UK waste management policy. (author)

  5. Dicty_cDB: FC-AP13 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available FC (Link to library) FC-AP13 (Link to dictyBase) - - - Contig-U15374-1 FC-AP13P (Li...nk to Original site) FC-AP13F 550 FC-AP13Z 184 FC-AP13P 734 - - Show FC-AP13 Library FC (Link to library) Clone ID FC-AP...al site URL http://dictycdb.biol.tsukuba.ac.jp/CSM/FC/FC-AP/FC-AP13Q.Seq.d/ Representative seq. ID FC-AP...13P (Link to Original site) Representative DNA sequence >FC-AP13 (FC-AP13Q) /CSM/FC/FC-AP/FC-AP...KKRKLNILIIII*fnnhqvmekkikkkiknkkn f*k Homology vs CSM-cDNA Score E Sequences producing significant alignments: (bits) Value FC-AP

  6. Reactor building

    International Nuclear Information System (INIS)

    The whole reactor building is accommodated in a shaft and is sealed level with the earth's surface by a building ceiling, which provides protection against penetration due to external effects. The building ceiling is supported on walls of the reactor building, which line the shaft and transfer the vertical components of forces to the foundations. The thickness of the walls is designed to withstand horizontal pressure waves in the floor. The building ceiling has an opening above the reactor, which must be closed by cover plates. Operating equipment for the reactor can be situated above the building ceiling. (orig./HP)

  7. Heterogeneous reactors

    International Nuclear Information System (INIS)

    The microscopic study of a cell is meant for the determination of the infinite multiplication factor of the cell, which is given by the four factor formula: K(infinite) = n(epsilon)pf. The analysis of an homogeneous reactor is similar to that of an heterogeneous reactor, but each factor of the four factor formula can not be calculated by the formulas developed in the case of an homogeneous reactor. A great number of methods was developed for the calculation of heterogeneous reactors and some of them are discussed. (Author)

  8. Network Cooperation for Client-AP Association Optimization

    OpenAIRE

    Baid, Akash; Schapira, Michael; Seskar, Ivan; Rexford, Jennifer; Raychaudhuri, Dipankar

    2012-01-01

    In a WiFi deployment with multiple access points, optimizing the way each client selects an AP from amongst the available choices, has a significant impact on the realized performance. When two or more such multi-AP networks are deployed in the same region, APs from different networks can cause severe interference to one another. In this paper, we study how inter-network interference effects the intra-network association optimization and propose a cooperative optimization scheme to mitigate t...

  9. Comprehensive investigation of the effectiveness of the AP-CITROX decontamination technology

    International Nuclear Information System (INIS)

    In the VVER-type pressurized water reactors, the so-called AP-CITROX method (AP: alkaline permanganate, CITROX: citric and oxalic acids) is widely used for the chemical decontamination of the austenitic stainless steel piping of steam generators. Comprehensive analysis of the characteristic technological data compiled at Paks NPP in the period of 1993 - 2000 has revealed that the average values of the decontamination factors (DFs) are rather low (DF<20); furthermore, the uncertainty of the data is extremely high. In order to achieve more effective decontamination (i.e. to increase the DF values by one order of magnitude) optimization of the applied technological parameters such as flow rate, contact time, chemical concentration and temperature is highly recommended. For these studies a pilot-plant circulation system was developed. The very aim of the present work is to determine the optimal flow rate, at which the decontamination factor of the heat exchanger tubes increases remarkably without detrimental changes in the passivity of the surfaces. From the γ-spectrometric, ICP-OES and voltammetric results it can be concluded that: (i) A significant increase in the flow rate of the decontamination solution up to 2.89 m/s in the 1-5 steps of the AP-CITROX procedure is highly recommended. (ii) During the passivation (in the 6-8 steps) the flow rate should be kept as low as possible (0.5 m/s) in order to improve the passivity of the surfaces. (authors)

  10. Global deployment of AP1000TM third-generation-plus nuclear power plant

    International Nuclear Information System (INIS)

    Westinghouse Electric Company (WEC) is promoting expanded global deployment of the AP1000TM pressurized water reactor (PWR), which is the only third-generation-plus nuclear power plant to have received design certification from the United States Nuclear Regulatory Commission (NRC). Based on the proven performance of WEC-designed PWRs, the AP1000TM not only achieves a significant reduction in the amount of equipment required compared with conventional PWR systems by making use of passive safety-related systems, but also makes it possible to reduce construction costs and shorten the construction period by means of advanced construction technologies such as modular construction techniques, steel-plate-reinforced concrete (SC) structures, and so on. In China, four AP1000TM plants - two in Sanmen and two in Haiyang - are under construction on schedule. In the United States as well, the pre-construction of two out of six contracted plants is currently underway at the Vogtle site in Georgia and the V.C. Summer site in South Carolina. WEC is accelerating proposal activities in response to the increase in nuclear power plant construction plans in many countries throughout the world. (author)

  11. Market analysis of APS/SCM applications and technologies

    OpenAIRE

    Prášil, Zdeněk

    2009-01-01

    The bachelor thesis aims to describe a current worldwide market of APS/SCM technologies and applications , i.e. advanced planned scheduling /supply chain management. In the first part, the APS/SCM is described in theory. The APS/SCM is defined and its benefits and impacts on company are discussed. The next part of the work is focused on the market with APS/SCM and the distribution of forces in the market. The demand and supply of this market segment is analyzed. In the last part, solutions of...

  12. Reactor technology comparison method using modeling and decision making technique

    International Nuclear Information System (INIS)

    To make wise choices about the future of nuclear power, we need improved knowledge of the safety, safeguards, and security features of both existing and new nuclear energy plants. Understanding the potential advantages and disadvantages of nuclear energy is critical for those stake holders and decision-makers facing Korea's energy challenges. This report provides an overview of the evolution of nuclear reactor technology and discusses development and deployment of reactor technology in future Korea. Following reactor technology options will be considered within this report: 1) Active Reactor (GEN Π : OPR 1000) 2) Advanced Reactor (GEN ΠI : APR 1400) 3) Passive Reactor (GEN ΠI+ : AP 1000 ) 4) Small Modular Reactor (GEN ΙV )

  13. Project W-211, initial tank retrieval systems, description of operations for 241-AP-102 and 241-AP-104

    International Nuclear Information System (INIS)

    The primary purpose of the Initial Tank Retrieval Systems (ITRS) is to provide systems for retrieval of radioactive wastes stored in underground double-shell tanks (DSTS) for transfer to alternate storage, evaporation, pretreatment or treatment, while concurrently reducing risks associated with safety watch list and other DSTs. This Description of Operations (DOO) defines the control philosophy for the waste retrieval system for tanks 241-AP-102 (AP-102) and 241-AP-104 (AP-104). This DOO will provide a basis for the detailed design of the Retrieval Control System (RCS) for AP-102 and AP-104 and establishes test criteria for the RCS. The test criteria will be used during qualification testing and acceptance testing to verify operability

  14. Project W-211, initial tank retrieval systems, description of operations for 241-AP-102 and 241-AP-104

    Energy Technology Data Exchange (ETDEWEB)

    RIECK, C.A.

    1999-02-25

    The primary purpose of the Initial Tank Retrieval Systems (ITRS) is to provide systems for retrieval of radioactive wastes stored in underground double-shell tanks (DSTS) for transfer to alternate storage, evaporation, pretreatment or treatment, while concurrently reducing risks associated with safety watch list and other DSTs. This Description of Operations (DOO) defines the control philosophy for the waste retrieval system for tanks 241-AP-102 (AP-102) and 241-AP-104 (AP-104). This DOO will provide a basis for the detailed design of the Retrieval Control System (RCS) for AP-102 and AP-104 and establishes test criteria for the RCS. The test criteria will be used during qualification testing and acceptance testing to verify operability.

  15. Plasma reactor

    OpenAIRE

    Molina Mansilla, Ricardo; Erra Serrabasa, Pilar; Bertrán Serra, Enric

    2008-01-01

    [EN] A plasma reactor that can operate in a wide pressure range, from vacuum and low pressures to atmospheric pressure and higher pressures. The plasma reactor is also able to regulate other important settings and can be used for processing a wide range of different samples, such as relatively large samples or samples with rough surfaces.

  16. Reactor physics

    International Nuclear Information System (INIS)

    Progress in research on reactor physics in 1997 at the Belgian Nuclear Research Centre SCK/CEN is described. Activities in the following four domains are discussed: core physics, ex-core neutron transport, experiments in Materials Testing Reactors, international benchmarks

  17. Genome-Wide Identification of the Target Genes of AP2-O, a Plasmodium AP2-Family Transcription Factor.

    Science.gov (United States)

    Kaneko, Izumi; Iwanaga, Shiroh; Kato, Tomomi; Kobayashi, Issei; Yuda, Masao

    2015-05-01

    Stage-specific transcription is a fundamental biological process in the life cycle of the Plasmodium parasite. Proteins containing the AP2 DNA-binding domain are responsible for stage-specific transcriptional regulation and belong to the only known family of transcription factors in Plasmodium parasites. Comprehensive identification of their target genes will advance our understanding of the molecular basis of stage-specific transcriptional regulation and stage-specific parasite development. AP2-O is an AP2 family transcription factor that is expressed in the mosquito midgut-invading stage, called the ookinete, and is essential for normal morphogenesis of this stage. In this study, we identified the genome-wide target genes of AP2-O by chromatin immunoprecipitation-sequencing and elucidate how this AP2 family transcription factor contributes to the formation of this motile stage. The analysis revealed that AP2-O binds specifically to the upstream genomic regions of more than 500 genes, suggesting that approximately 10% of the parasite genome is directly regulated by AP2-O. These genes are involved in distinct biological processes such as morphogenesis, locomotion, midgut penetration, protection against mosquito immunity and preparation for subsequent oocyst development. This direct and global regulation by AP2-O provides a model for gene regulation in Plasmodium parasites and may explain how these parasites manage to control their complex life cycle using a small number of sequence-specific AP2 transcription factors. PMID:26018192

  18. Water desalination using different capacity reactors options

    International Nuclear Information System (INIS)

    The Northwest region of Mexico has a deficit of potable water, along this necessity is the region growth, which requires of additional energy capacity, cogeneration of potable water production and nuclear electricity is an option to be assessed. In this paper we will perform an economical comparison for cogeneration using a big reactor, the AP1000, and a medium size reactor, the IRIS, both of them are PWR type reactors and will be coupled to the desalination plant using the same method. For this cogeneration case we will assess the best reactor option that can cover both needs using the maximum potable water production for two different desalination methods: Multistage Flash Distillation and Multi-effect Distillation. (authors)

  19. Experimental analysis of heat transfer within the AP600 containment under postulated accident conditions

    International Nuclear Information System (INIS)

    The new AP600 reactor designed by Westinghouse uses a passive safety system relying on heat removal by condensation to keep the containment within the design limits of pressure and temperature. Even though some research has been done so far in this regard, there are some uncertainties concerning the behavior of the system under postulated accident conditions. In this paper, steam condensation onto the internal surfaces of the AP600 containment walls has been investigated in two scaled vessels with similar aspect ratios to the actual AP600. The heat transfer degradation in the presence of noncondensable gas has been analyzed for different noncondensable mixtures of air and helium (hydrogen simulant). Molar fractions of noncondensables/steam ranged from (0.4-4.0) and helium concentrations in the noncondensable mixture were 0-50% by volume. In addition, the effects of the bulk temperatures, the mass fraction of noncondensable/steam, the cold wall surface temperature, the pressure, noncondensable composition, and the inclination of the condensing surface were studied. It was found that the heat transfer coefficients ranged from 50 to 800 J s-1 K-1 m-2 with the highest for high wall temperatures at high pressure and low noncondensable molar fractions. The effect of a light gas (helium) in the noncondensable mixture were found to be negligible for concentrations less than approximately 35 molar percent but could result in stratification at higher concentrations. The complete study gives a large and relatively complete data base on condensation within a scaled AP600 containment structure, providing an invaluable set of data against which to validate models. In addition, specific areas requiring further investigation are summarized. (orig.)

  20. Residual radiation studies at AP0

    Energy Technology Data Exchange (ETDEWEB)

    Alexander J Elwyn et al.

    2002-06-19

    The radiation environment at the NuMI experiment has received a lot of attention in the last few years in preparation for project construction. One important issue is the induced radioactivation of the components in the beam line and the shielding materials. This arises from irradiation by hadrons that are generated in the target. Since the level of the residual activity has to be considered when determining access procedures for maintenance during NuMI operation, an understanding of the properties of the remnant radiation is important. To this end, experimental studies were performed in the target vault at AP0 which is similar in design to the NuMI target area. Here 120 GeV protons bombard a target, generating the hadrons that produce the induced radioactivity. Two sets of samples each consisting of three small cylindrical or rectangular solids of iron and steel, one sample of aluminum, and one of concrete were irradiated. One set was hung just below the bottom of a module near the lithium lens (in-vault), and the other was placed on top of the modules downstream of this location (above-vault), just beneath the movable concrete roof of the vault at AP0. Further, four thin activation foils of Au, Au+Cd, In, and Al (along with small disks of the same iron, aluminum, and concrete samples discussed above) were mounted on four 10.2 cm diameter Al disks, one placed on the in-vault module and three at above-vault downstream locations as well. The radioactivity of all these materials on the 10.2 cm Al disks was determined at the Radioisotope Analysis Facility in an attempt to characterize the radionuclides produced during irradiation. The activities of the thin foils were employed in an effort to unfold a spectrum of the neutrons produced during the hadronic cascades in the target. The MARS Monte Carlo code (MO95, MO00) was used to predict and analyze the residual radiation produced during the beam irradiation. New subroutines have been developed for the MARS14 version

  1. Status of the Advanced Photon Source (APS) linear accelerator

    International Nuclear Information System (INIS)

    A 2856-MHz S-band, 450-MeV electron/positron linear accelerator is the first part of the injector for the Advanced Photon Source (APS) 7-GeV storage ring. Construction of the APS linac is currently nearing completion, and commissioning will begin in July 1993. The linac and its current status are discussed in this paper

  2. A Closer Examination of the Academic Benefits of AP

    Science.gov (United States)

    McKillip, Mary E. M.; Rawls, Anita

    2013-01-01

    The authors sought to better understand the relationship between students participating in the Advanced Placement (AP) program and subsequent performance on the Scholastic Aptitude Test (SAT). Focusing on students graduating from U.S. public high schools in 2010, the authors used propensity scores to match junior year AP examinees in 3 subjects to…

  3. AP-42 ADDITIONS AND REVISIONS - LANDFILLS (COMBUSTION CONTROLS)

    Science.gov (United States)

    This project develops emission factors, etc., for landfills, in particular for combustion devices fed by landfill gas, for incorporation into AP-42. AP-42 is a massive collection of information concerning processes which generate air emissions and presents emission factors and co...

  4. Data-Based Decision Making: The Road to AP Equity

    Science.gov (United States)

    Edwards, Kelcey; Duggan, Odette

    2012-01-01

    Presented at the Advanced Placement Annual Conference (APAC) in Lake Buena Vista, FL in July 2012. This presentation reviews concepts central to achieving equitable AP access and success for all willing and academically prepared students. We analyze trends in participation and performance by race/ethnicity from the AP Report to the Nation and…

  5. APS extends open access to all its journals

    CERN Multimedia

    Thomas, Kim

    2006-01-01

    "Physics research promoter and publisher the American Physical Society (APS) is to extend open access to all its journals. Th APS previously made its five print journals available through subscriptions, and its two e-journals (Physical Review Special Topics and Physics Educatoin Research) on an open access basis." (1/2 page)

  6. Training and development of the Assistant Practitioners (APs) in radiography

    International Nuclear Information System (INIS)

    A mixed methods study conducted over three phases (Phase I – scoping exercise, Phase II – questionnaire and Phase III – semi-structured interviews) aimed to explore the role and integration of the assistant practitioner (AP) practitioner in radiography from the AP perspective. Findings of the overall study are presented across a range of articles where this publication only presents the findings in relation to the training and education of APs from all three phases. Results showed the educational routes undertaken by APs in radiography during training. Training whilst working in the clinical department has highlighted a number of key issues relating to educational pathways and delivery methods. Findings showed that APs felt that more could be done to prepare the individual for clinical practice thereby increasing their confidence and facilitating role development. Results also identified a number of challenges in the training and education of APs in radiography. Clear routes of progression and career pathways are not available to APs in radiography. In conclusion the findings suggest the need for a review of existing educational programmes and future standardisation. The need exists to clarify the justifiable methods of training and differentiate between recognised educational qualifications to enable informed career development decisions by APs and their employers

  7. Application case study of AP1000 automatic depressurization system (ADS) for reliability evaluation by GO-FLOW methodology

    International Nuclear Information System (INIS)

    Highlights: • Discussion on reasons why AP1000 equipped with ADS system comparatively to PWR. • Clarification of full and partial depressurization of reactor coolant system by ADS system. • Application case study of four stages ADS system for reliability evaluation in LBLOCA. • GO-FLOW tool is capable to evaluate dynamic reliability of passive safety systems. • Calculated ADS reliability result significantly increased dynamic reliability of PXS. - Abstract: AP1000 nuclear power plant (NPP) utilized passive means for the safety systems to ensure its safety in events of transient or severe accidents. One of the unique safety systems of AP1000 to be compared with conventional PWR is the “four stages Automatic Depressurization System (ADS)”, and ADS system originally works as an active safety system. In the present study, authors first discussed the reasons of why four stages ADS system is added in AP1000 plant to be compared with conventional PWR in the aspect of reliability. And then explained the full and partial depressurization of RCS system by four stages ADS in events of transient and loss of coolant accidents (LOCAs). Lastly, the application case study of four stages ADS system of AP1000 has been conducted in the aspect of reliability evaluation of ADS system under postulated conditions of full RCS depressurization during large break loss of a coolant accident (LBLOCA) in one of the RCS cold legs. In this case study, the reliability evaluation is made by GO-FLOW methodology to determinate the influence of ADS system in dynamic reliability of passive core cooling system (PXS) of AP1000, i.e. what will happen if ADS system fails or successfully actuate. The GO-FLOW is success-oriented reliability analysis tool and is capable to evaluating the systems reliability/unavailability alternatively to Fault Tree Analysis (FTA) and Event Tree Analysis (ETA) tools. Under these specific conditions of LBLOCA, the GO-FLOW calculated reliability results indicated

  8. Compact Reactor

    International Nuclear Information System (INIS)

    Weyl's Gauge Principle of 1929 has been used to establish Weyl's Quantum Principle (WQP) that requires that the Weyl scale factor should be unity. It has been shown that the WQP requires the following: quantum mechanics must be used to determine system states; the electrostatic potential must be non-singular and quantified; interactions between particles with different electric charges (i.e. electron and proton) do not obey Newton's Third Law at sub-nuclear separations, and nuclear particles may be much different than expected using the standard model. The above WQP requirements lead to a potential fusion reactor wherein deuterium nuclei are preferentially fused into helium nuclei. Because the deuterium nuclei are preferentially fused into helium nuclei at temperatures and energies lower than specified by the standard model there is no harmful radiation as a byproduct of this fusion process. Therefore, a reactor using this reaction does not need any shielding to contain such radiation. The energy released from each reaction and the absence of shielding makes the deuterium-plus-deuterium-to-helium (DDH) reactor very compact when compared to other reactors, both fission and fusion types. Moreover, the potential energy output per reactor weight and the absence of harmful radiation makes the DDH reactor an ideal candidate for space power. The logic is summarized by which the WQP requires the above conditions that make the prediction of DDH possible. The details of the DDH reaction will be presented along with the specifics of why the DDH reactor may be made to cause two deuterium nuclei to preferentially fuse to a helium nucleus. The presentation will also indicate the calculations needed to predict the reactor temperature as a function of fuel loading, reactor size, and desired output and will include the progress achieved to date

  9. The development of beam current monitors in the APS

    International Nuclear Information System (INIS)

    The Advanced Photon Source (APS) is a third-generation 7-GeV synchrotron radiation source. The precision measurement of beam current is a challenging task in high energy accelerators, such as the APS, with a wide range of beam parameters and complicated noise, radiation, and thermal environments. The beam pulses in the APS injector and storage ring have charge ranging from 50pC to 25nC with pulse durations varying from 30ps to 30ns. A total of nine non- intercepting beam current monitors have been installed in the APS facility (excluding those in the linac) for general current measurement. In addition, several independent current monitors with specially designed redundant interlock electronics are installed for personnel safety and machine protection. This paper documents the design and development of current monitors in the APS,. discusses the commissioning experience in the past year, and presents the results of recent operations

  10. Properties of LuAP: CE scintillator containing intentional impurities

    CERN Document Server

    Petrosyan, A G; Ovanesyan, K; Lecoq, Paul; Auffray, Etiennette; Trummer, Julia; Kronberger, Matthias; Pédrini, C; Dujardin, C; Anfre, P

    2007-01-01

    Single crystals of LuAP:Ce and LuYAP(Lu*70%):Ce co-doped with tetravalent (Hf and Zr) and pentavalent (Ta) ions were grown from melts by the Bridgman process. Underlying absorption, slope of the optical edge and transmission in the range of emission were compared to those of LuAP:Ce crystals. Absorption coefficients at 260 nm less than 2 cm−1 have been recorded in LuAP:Ce crystals containing tetravalent ions that are lower than the corresponding figures (5–6 cm−1) measured in undoped LuAP. At high concentrations of added impurities, despite of suppression of the parasitic underlying absorption below 300 nm, the slope of the optical edge and transmission in the range of emission are seriously damaged. Scintillation parameters of crystals with added impurities are compared to those of LuAP:Ce.

  11. Using metallic filters in APS undulator beamlines

    International Nuclear Information System (INIS)

    Metallic filters are needed by APS users in their beamlines. Two general areas of use for the white-beam metallic filters are: (1) to attenuate the x-ray beam to reduce the thermal load during routine operations and (2) to attenuate the x-ray beam during alignment and for special testing of optics at low power. Metallic filters are important for users who will be working primarily in the high energy x-ray range because unwanted lower energy photons are absorbed through the metallic filters. Notwithstanding their high thermal conductivity, the metals, in general, absorb x-rays significantly near surface layers and hence can attain very large temperatures causing structural deformations and/or damage. Thermomechanical behavior and failure prediction need to be done carefully. In this paper, particulars of metallic filters are discussed and generalized analytical solutions are offered to help users of metallic filters determine their applicability for x-ray beamlines copyright 1996 American Institute of Physics

  12. Top-up operation experience at APS

    International Nuclear Information System (INIS)

    The Advanced Photon Source (APS) is a 7-OeV, third-generation synchrotrons radiation source. To provide more stable beam for users, in September 1998 we began commissioning a new operating mode called ''top-up.'' In this mode, the beam current does not decay but is maintained at a high level using frequent injection, while photon shutters are open and photon beams are delivered to users. The hardware, software, and safety requirements for top-up will be reported. Safety issues related to injection with open photon shutters are covered in companion papers in this conference. Recent operational experience includes testing aspects of top-up injection and delivering beam to X-ray users for a few hours with fractional current stability of 10-3. We expect to run several top-up operation shifts in Spring 1999. Issues of importance are orbit and emittance transients during the injection and scheduling of injection pulses for the convenience of users

  13. Beam instability studies at the APS

    International Nuclear Information System (INIS)

    The Argonne Advanced Photon Source, APS (Fig. 1), is a 7-GeV positron storage ring with a circumference of 1104 m. It has a ''third generation, DBA or Chasman-Green'' lattice composed of 40 sectors each having a ∼6 m long zero-dispersion straight-section for accommodating insertion devices. Neighboring straight-sections are connected by a 360 degrees/40 = 9 degrees double-bend-achromatic bending section designed to produce the smallest emittance attainable with reasonable component parameter values and dynamic apertures. Thus, it is a very strongly focusing lattice with vx = 35.22 and vy = 14.30. The beam chamber of the storage ring including all rf, vacuum and photon beam components is designed to ensure that a beam current > 100 mA can be stably stored. We expect that the maximum stable beam current could be as high as 300 mA. This paper will give some details of the studies and computations to ensure the stability of such a beam. The discussions will be organized in the following three parts: Coupled-bunch instability caused by the higher-order modes (HOMs) of the rf cavities; Single-bunch instability due to the resistive wall impedance; and Single-bunch instability due to broadband impedances arising from beam chamber irregularities

  14. Burnup study of 18 months and 16/20 months cycle AP1000 cores using CASMO4E and SIMULATE-3 codes

    International Nuclear Information System (INIS)

    AP1000 reactor is an advanced pressurized water reactor equipped with passive safety systems. AP1000 reactor core is designed for 18 month cycle length and can also be used for 16/20 month alternate cycle lengths to meet energy requirements during high demand periods. The purpose of this study is to analyze the feasibility of AP1000 core for both 18 and 16/20 alternate cycle lengths by using CASMO4E and SIMULATE-3 code package. For this purpose, burnup analysis of both the schemes is carried out from initial core loading through optimized transition cores to equilibrium core. The study is performed by modeling three dimensional full core in SIMULATE-3 with each fuel assembly divided into 40 axial and 4 radial quadrant nodes. Once and twice burned fuel reloading from one cycle to the next and removal of burnable poison rods from the core after first cycle options are used in these codes. The results of this study indicate that both the cycle schemes can be utilized by varying the core loading pattern. Moreover, reactivity coefficients, total power peaking factors and enthalpy rise factors are calculated which indicate that the AP1000 core provide adequate safety margins in both the cycle schemes. (author)

  15. AP1000 construction and operating costs

    International Nuclear Information System (INIS)

    Market analysis of the U.S. electricity generating market indicates that the generating cost of competitive new generating capacity must be less than $0.03/kw-hr. When such factors as an attractive return on investment and payback period are considered for a new nuclear electric generating facility, this results in the requirement to have an overnight capital cost of approximately $1000/kw. Industry executives indicate that any new nuclear plant must be able to compete in the de-regulated generation wholesale marketplace and provide a return to the shareholders. Against this standard, the costs of advanced nuclear power plants currently available are still too high. In the United States, the Utility Requirements Document for advanced light water reactor plants included a cost goal that was based on the cost of coal generated electricity at the time the document was written. Since that time, the cost of new generating capacity and the overall operating cost of generating electricity has gone down. This is a result of low natural gas prices, more efficient plants in general and the current record breaking reductions in outage times and operating costs for nuclear plants. The plant designs resulting from the United States advanced light water reactor plant programs received Design Certification from the United States Nuclear Regulatory Commission. Some are being deployed, with variations, in countries other than the United States. But they can not compete today with other sources of central station generation in the United States. (author)

  16. Requirements for light water reactors

    International Nuclear Information System (INIS)

    The EUR (European Utilities Requirements) is an organization founded in 1991 whose aim was to write down the European specifications and requirements for the future reactors of third generation. EUR gathers most of the nuclear power producers of Europe. The EUR document has been built on the large and varied experience of EUR members and can be used to elaborate invitations to tender for nuclear projects. 4000 requirements only for the nuclear part of the plant are listed, among which we have: -) the probability of core meltdown for a reactor must be less than 10-6 per year, -) the service life of every component that is not replaceable must be 60 years, -) the capacity of the spent fuel pool must be sufficient to store 10-15 years of production without clearing out. The EUR document is both open and complete: every topic has been considered, it does not favor any type of reactor but can ban any technology that is too risky or has an unfavourable feedback experience. The assessment of the conformity with the EUR document of 7 reactor projects (BWR 90/, EPR, EP1000, SWR1000, ABWR, AP1000 and VVER-AES-92) has already be made. (A.C.)

  17. Dicty_cDB: FC-AP05 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available FC (Link to library) FC-AP05 (Link to dictyBase) - - - Contig-U16521-1 FC-AP05Z (Li...nk to Original site) - - FC-AP05Z 532 - - - - Show FC-AP05 Library FC (Link to library) Clone ID FC-AP05 (Li.../dictycdb.biol.tsukuba.ac.jp/CSM/FC/FC-AP/FC-AP05Q.Seq.d/ Representative seq. ID FC-AP...05Z (Link to Original site) Representative DNA sequence >FC-AP05 (FC-AP05Q) /CSM/FC/FC-AP/FC-AP05Q.Seq....GAGA TCCGTCAAAGTTTCAAGCAAAAAAGTTGTTGCCAAGTAAATAAATAATACTTTTTTCCCT AT sequence update 1997. 3.25 Translated Amino Acid sequence ---AP

  18. Dicty_cDB: FC-AP23 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available FC (Link to library) FC-AP23 (Link to dictyBase) - G03230 DDB0190153 Contig-U16094-1 FC-AP...23P (Link to Original site) FC-AP23F 515 FC-AP23Z 472 FC-AP23P 987 - - Show FC-AP23 Library FC (Link ...ontig Contig-U16094-1 Original site URL http://dictycdb.biol.tsukuba.ac.jp/CSM/FC/FC-AP/FC-AP...23Q.Seq.d/ Representative seq. ID FC-AP23P (Link to Original site) Representative DNA sequence >FC-AP23 (FC-AP...23Q) /CSM/FC/FC-AP/FC-AP23Q.Seq.d/ CAAATACATAATCTCTTTTTTGAAAATGTCCGAAAATAACGAAATTGAAATGGAACTCC

  19. Dicty_cDB: FC-AP12 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available FC (Link to library) FC-AP12 (Link to dictyBase) - G01739 DDB0232214 Contig-U15924-1 FC-AP...12P (Link to Original site) FC-AP12F 323 FC-AP12Z 613 FC-AP12P 936 - - Show FC-AP12 Library FC (Link ...ontig Contig-U15924-1 Original site URL http://dictycdb.biol.tsukuba.ac.jp/CSM/FC/FC-AP/FC-AP...12Q.Seq.d/ Representative seq. ID FC-AP12P (Link to Original site) Representative DNA sequence >FC-AP12 (FC-AP...12Q) /CSM/FC/FC-AP/FC-AP12Q.Seq.d/ CATATTATTTTAAATTTCAGATGTTCCCAAAATAACACATTAATTTGCTTTTTTTGTTG

  20. NEUTRONIC REACTOR

    Science.gov (United States)

    Anderson, H.L.

    1960-09-20

    A nuclear reactor is described comprising fissionable material dispersed in graphite blocks, helium filling the voids of the blocks and the spaces therebetween, and means other than the helium in thermal conductive contact with the graphite for removing heat.

  1. NUCLEAR REACTOR

    Science.gov (United States)

    Miller, H.I.; Smith, R.C.

    1958-01-21

    This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.

  2. Nuclear reactors

    International Nuclear Information System (INIS)

    This draft chart contains graphical symbols from which the type of (nuclear) reactor can be seen. They will serve as illustrations for graphical sketches. Important features of the individual reactor types are marked out graphically. The user can combine these symbols to characterize a specific reactor type. The basic graphical symbol is a square with a point in the centre. Functional groups can be depicted for closer specification. If two functional groups are not clearly separated, this is symbolized by a dotted line or a channel. Supply and discharge lines for coolant, moderator and fuel are specified in accordance with DIN 2481 and can be further specified by additional symbols if necessary. The examples in the paper show several different reactor types. (orig./AK)

  3. AP1000TM Nuclear Power Plant - Passive Safety System Actuation using Explosively Opening 'Squib Valves'

    International Nuclear Information System (INIS)

    In the last decades the world demand for energy was growing rapidly and despite the economic crisis no basic change in this development can be expected for the future. Especially the developing countries with fast growing populations and economies will have an increasing need for energy in all forms while available resources are decreasing. The extreme volatility of energy prices in the last years has shown how dependent on cheap and reliable energy we are and how dangerous it is to focus only on few sources. On the other hand the excessive use of fossil fuel in the last century has led to a man made climate change by emission of greenhouse gases. The renaissance of nuclear power is one of the answers to these issues. Global warming cannot be avoided on a short but carbon free nuclear technology can help limiting the effects of climate change and provide billions of people with cheap and reliable energy at the same time. However, a worldwide 'nuclear renaissance' has some prerequisites. Beside economic competitiveness advanced nuclear safety based on proven, evolutionary technologies is the most important condition for the acceptance of new nuclear power plants. Half of the world's nuclear reactors are based on proven Westinghouse design. These plants have more than 10,000 years of operating experience. The AP1000TM plant is the result of an evolutionary development process where advanced, passive safety features have been combined with proven components from operating plants. Significant design simplifications together with the reduction of piping, cabling, pumps, valves and seismic grade building size have led to reduced investment costs. A consequent modularization enables the plant to be constructed within three years. Passive safety functions relying only on natural forces make the plant safer than any existing reactor. Because active decay heat removal systems do not have to be safety grade classified any more, construction, inspection and maintenance are

  4. AP1000TM Nuclear Power Plant Passive Safety System Actuation using Explosively Opening 'Squib Valves'

    International Nuclear Information System (INIS)

    In the last decades the world demand for energy was growing rapidly and despite the economic crisis no basic change in this development can be expected for the future. Especially the developing countries with fast growing populations and economies will have an increasing need for energy in all forms while available resources are decreasing. The extreme volatility of energy prices in the last years has shown how dependent on cheap and reliable energy we are and how dangerous it is to focus only on few sources. On the other hand the excessive use of fossil fuel in the last century has led to a man made climate change by emission of greenhouse gases. The renaissance of nuclear power is one of the answers to these issues. Global warming cannot be avoided on a short but carbon free nuclear technology can help limiting the effects of climate change and provide billions of people with cheap and reliable energy at the same time. However, a worldwide 'nuclear renaissance' has some prerequisites. Beside economic competitiveness advanced nuclear safety based on proven, evolutionary technologies is the most important condition for the acceptance of new nuclear power plants. Half of the world's nuclear reactors are based on proven Westinghouse design. These plants have more than 10,000 years of operating experience. The AP1000TM plant is the result of an evolutionary development process where advanced, passive safety features have been combined with proven components from operating plants. Significant design simplifications together with the reduction of piping, cabling, pumps, valves and seismic grade building size have led to reduced investment costs. A consequent modularization enables the plant to be constructed within three years. Passive safety functions relying only on natural forces make the plant safer than any existing reactor. Because active decay heat removal systems do not have to be safety grade classified any more, construction, inspection and maintenance are

  5. Multifunctional reactors

    OpenAIRE

    Westerterp, K.R.

    1992-01-01

    Multifunctional reactors are single pieces of equipment in which, besides the reaction, other functions are carried out simultaneously. The other functions can be a heat, mass or momentum transfer operation and even another reaction. Multifunctional reactors are not new, but they have received much emphasis in research in the last decade. A survey is given of modern developments and the first successful applications on a large scale. It is explained why their application in many instances is ...

  6. NUCLEAR REACTOR

    Science.gov (United States)

    Anderson, C.R.

    1962-07-24

    A fluidized bed nuclear reactor and a method of operating such a reactor are described. In the design means are provided for flowing a liquid moderator upwardly through the center of a bed of pellets of a nentron-fissionable material at such a rate as to obtain particulate fluidization while constraining the lower pontion of the bed into a conical shape. A smooth circulation of particles rising in the center and falling at the outside of the bed is thereby established. (AEC)

  7. Nuclear reactor

    International Nuclear Information System (INIS)

    In order to reduce neutron embrittlement of the pressue vessel of an LWR, blanked off elements are fitted at the edge of the reactor core, with the same dimensions as the fuel elements. They are parallel to each other, and to the edge of the reactor taking the place of fuel rods, and are plates of neutron-absorbing material (stainless steel, boron steel, borated Al). (HP)

  8. Breeder reactors

    International Nuclear Information System (INIS)

    The reasons for the development of fast reactors are briefly reviewed (a propitious neutron balance oriented towards a maximum uranium burnup) and its special requirements (cooling, fissile material density and reprocessing) discussed. The three stages in the French program of fast reactor development are outlined with Rapsodie at Cadarache, Phenix at Marcoule, and Super Phenix at Creys-Malville. The more specific features of the program of research and development are emphasized: kinetics and the core, the fuel and the components

  9. Bottom-mounted Reactor Shutdown Mechanism

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sanghaun; Lee, Jin Haeng; Cho, Yeonggarp; Yoo, Yeonsik; Kim, Dongmin; Kim, Jongin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-05-15

    The CRDM acts as the first reactor shutdown mechanism and reactor regulating as well. The SSDM provides an alternate and independent means of reactor shutdown. The second shutdown rods (SSRs) of the SSDM are poised at the top of the core by the hydraulic system during the normal operation and drop by gravity within the specific time for a reactor trip. The SSR drop is actuated by the Reactor Protection System (RPS), Alternate Protection System (APS), Automatic Seismic Trip System (ASTS), or by the reactor operator in KJRR. Based on the proven technology of the design, operation and maintenance for HANARO and JRTR (Jordan Research and Training Reactor), the SSDM for the KJRR has been optimized by the design improvement from the experience and test. This paper aims for the introduction of the BM SSDM in the process of the basic design. The major differences of the shutdown mechanisms are comparatively analyzed between HANARO and KJRR. And the design features, system, structure and future works are also suggested. A basic design of the BM SSDM for the KJRR has been completed on the basis of the HANARO's SO unit or JRTR's SSDM. The SSR and its guide tube are designed and optimized according to the geometrical core configuration.

  10. Bottom-mounted Reactor Shutdown Mechanism

    International Nuclear Information System (INIS)

    The CRDM acts as the first reactor shutdown mechanism and reactor regulating as well. The SSDM provides an alternate and independent means of reactor shutdown. The second shutdown rods (SSRs) of the SSDM are poised at the top of the core by the hydraulic system during the normal operation and drop by gravity within the specific time for a reactor trip. The SSR drop is actuated by the Reactor Protection System (RPS), Alternate Protection System (APS), Automatic Seismic Trip System (ASTS), or by the reactor operator in KJRR. Based on the proven technology of the design, operation and maintenance for HANARO and JRTR (Jordan Research and Training Reactor), the SSDM for the KJRR has been optimized by the design improvement from the experience and test. This paper aims for the introduction of the BM SSDM in the process of the basic design. The major differences of the shutdown mechanisms are comparatively analyzed between HANARO and KJRR. And the design features, system, structure and future works are also suggested. A basic design of the BM SSDM for the KJRR has been completed on the basis of the HANARO's SO unit or JRTR's SSDM. The SSR and its guide tube are designed and optimized according to the geometrical core configuration

  11. Research reactors - an overview

    Energy Technology Data Exchange (ETDEWEB)

    West, C.D.

    1997-03-01

    A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs.

  12. Dicty_cDB: FC-AP17 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available 4.1 SJMBIB09 SJM Schistosoma japonicum cDNA, mRNA sequence. 80 8e-20 2 BE859184 |BE859184.1 SsS0499 Suaeda salsa ZAP...FC (Link to library) FC-AP17 (Link to dictyBase) - - - Contig-U16254-1 FC-AP17Z (Li...nk to Original site) - - FC-AP17Z 546 - - - - Show FC-AP17 Library FC (Link to library) Clone ID FC-AP17 (Li.../dictycdb.biol.tsukuba.ac.jp/CSM/FC/FC-AP/FC-AP17Q.Seq.d/ Representative seq. ID FC-AP...17Z (Link to Original site) Representative DNA sequence >FC-AP17 (FC-AP17Q) /CSM/FC/FC-AP/FC-AP17Q.Seq.

  13. Dicty_cDB: FC-AP11 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available A clone IMAGE:4920557 5', mRNA sequence. 56 1e-04 2 BF345929 |BF345929.1 602017931F1 NCI_CGAP_Brn67 Homo sap...FC (Link to library) FC-AP11 (Link to dictyBase) - - - Contig-U16101-1 FC-AP11F (Li...nk to Original site) FC-AP11F 394 - - - - - - Show FC-AP11 Library FC (Link to library) Clone ID FC-AP11 (Li.../dictycdb.biol.tsukuba.ac.jp/CSM/FC/FC-AP/FC-AP11Q.Seq.d/ Representative seq. ID FC-AP...11F (Link to Original site) Representative DNA sequence >FC-AP11 (FC-AP11Q) /CSM/FC/FC-AP/FC-AP11Q.Seq.

  14. Dicty_cDB: FC-AP18 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available FC (Link to library) FC-AP18 (Link to dictyBase) - - - Contig-U16455-1 FC-AP18Z (Li...nk to Original site) - - FC-AP18Z 367 - - - - Show FC-AP18 Library FC (Link to library) Clone ID FC-AP18 (Li.../dictycdb.biol.tsukuba.ac.jp/CSM/FC/FC-AP/FC-AP18Q.Seq.d/ Representative seq. ID FC-AP...18Z (Link to Original site) Representative DNA sequence >FC-AP18 (FC-AP18Q) /CSM/FC/FC-AP/FC-AP18Q.Seq....XELTPSRPMCVESFNEYPP LGRFAVRDMGQTVAVGVIKSTVKKAPGKAGDKKGAXAPSKKK*innis**iafynnfkkk kkkkk Translated Amino Acid

  15. Dicty_cDB: FC-AP16 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available FC (Link to library) FC-AP16 (Link to dictyBase) - - - Contig-U16269-1 FC-AP16Z (Li...nk to Original site) - - FC-AP16Z 552 - - - - Show FC-AP16 Library FC (Link to library) Clone ID FC-AP16 (Li.../dictycdb.biol.tsukuba.ac.jp/CSM/FC/FC-AP/FC-AP16Q.Seq.d/ Representative seq. ID FC-AP...16Z (Link to Original site) Representative DNA sequence >FC-AP16 (FC-AP16Q) /CSM/FC/FC-AP/FC-AP16Q.Seq....7. 3.28 Translated Amino Acid sequence ---RNRRYKVRKGPLVVVSGKTTVSQALRNIPGVEVANVSRLNLLKLAPGGHLGRFIIWT KSAFEQLD

  16. Dicty_cDB: FC-AP15 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available FC (Link to library) FC-AP15 (Link to dictyBase) - - - Contig-U15444-1 FC-AP15Z (Li...nk to Original site) - - FC-AP15Z 594 - - - - Show FC-AP15 Library FC (Link to library) Clone ID FC-AP15 (Li.../dictycdb.biol.tsukuba.ac.jp/CSM/FC/FC-AP/FC-AP15Q.Seq.d/ Representative seq. ID FC-AP...15Z (Link to Original site) Representative DNA sequence >FC-AP15 (FC-AP15Q) /CSM/FC/FC-AP/FC-AP15Q.Seq....AAAAAAAAAAAAAAAAAA AAAA sequence update 1997. 3.25 Translated Amino Acid sequence ---RLLKIAEARAATPKGQAAPKAEK

  17. Condensation in the presence of noncondensible gases: AP600 containment simulation

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, M.H.; Corradini, M.L.

    1995-09-01

    The Westinghouse Electric Corporation has designed an advanced pressurized light water reactor, AP600. This reactor is designed with a passive cooling system to remove sensible and decay heat from the containment. The heat removal path involves condensation heat transfer, aided by natural convective forces generated by buoyancy effects. A one-twelfth scale rectangular slice of the proposed reactor containment was constructed at the University of Wisconsin to simulate conditions anticipated from transients and accidents that may occur in a full scale containment vessel under a variety of conditions. Similitude of the test facility was obtained by considering the appropriate dimensionless group for the natural convective process (modified Froude number) and the aspect ratio (H/R) of the containment vessel. An experimental investigation to determine the heat transfer coefficients associated with condensation on a vertical and horizontal cooled wall (located in the scaled test section) at several different inlet steam flow rates and test section temperatures was conducted. In this series of experiments, the non-condensible mass fraction varied between (0.9-0.4) with corresponding mixture temperatures between 60-90{degrees}C. The heat transfer coefficients of the top horizontal surface varied from (82-296)W/m{sup 2}K and the vertical side heat transfer coefficients varied form (70-269)m{sup 2}K. The results were then compared to boundary layer heat and mass transfer theory by the use of the McAdams correlation for free convection.

  18. Condensation in the presence of noncondensible gases: AP600 containment simulation

    International Nuclear Information System (INIS)

    The Westinghouse Electric Corporation has designed an advanced pressurized light water reactor, AP600. This reactor is designed with a passive cooling system to remove sensible and decay heat from the containment. The heat removal path involves condensation heat transfer, aided by natural convective forces generated by buoyancy effects. A one-twelfth scale rectangular slice of the proposed reactor containment was constructed at the University of Wisconsin to simulate conditions anticipated from transients and accidents that may occur in a full scale containment vessel under a variety of conditions. Similitude of the test facility was obtained by considering the appropriate dimensionless group for the natural convective process (modified Froude number) and the aspect ratio (H/R) of the containment vessel. An experimental investigation to determine the heat transfer coefficients associated with condensation on a vertical and horizontal cooled wall (located in the scaled test section) at several different inlet steam flow rates and test section temperatures was conducted. In this series of experiments, the non-condensible mass fraction varied between (0.9-0.4) with corresponding mixture temperatures between 60-90 degrees C. The heat transfer coefficients of the top horizontal surface varied from (82-296)W/m2K and the vertical side heat transfer coefficients varied form (70-269)m2K. The results were then compared to boundary layer heat and mass transfer theory by the use of the McAdams correlation for free convection

  19. The preliminary analysis of establishing the cost control system of AP1000 for the Haiyang nuclear power project

    International Nuclear Information System (INIS)

    The AP1000 technology has been first applied to Nuclear Power Plant construction in China. Haiyang Project is the second plant which applies the new technology, and it is the key to the success of the project, that how to control the cost. The cost control of AP1000 is to manage and monitor all the cost of the project, including the cost of project management, design, procurement, construction, and startup/commissioning. For the Haiyang Project, the cost control system should be established to ensure that the evaluation of the procurement order should be covered in the original budget, and all potential commitments are evaluated and approved within the confinement of cost control, and reduce the risk of the first reactor and get the most profit. (authors)

  20. Availability analysis of the AP600 passive core cooling system

    International Nuclear Information System (INIS)

    The reliability analysis of the AP600 Passive Core Cooling System (PXS) has been done. The fault tree analysis method was used for the quantitative analysis. The PXS can be grouped to several sub-systems i.e.: Reactor Coolant System (RCS) Injection Subsystem, Emergency Core Decay Heat Removal Subsystem, and Containment Sump pH Control Subsystem. The quantitative analysis results indicates that the system unavailability is highly dependent on the valves configuration of the Automatic Depressurization System (ADS). If the ADS valves is arranged in Option-1, the system unavailability is 2.347E-03, this means that the yearly contribution to plant down time can be estimated to be about 20.56 hours per year. Whereas, by using Option-2 of fourth stage ADS valves, the system unavailability is reduced to be 9.877E-04 or 8.65 hours per year and this value is consistent with the allocated goal value (8.0 hours per year). The ADS contributes 66.89% to the system unavailability if it is arranged in Option-1, and will reduced to be about 21.21% if its fourth stages are arranged in Option-2. If the ADS is not included as a subsystem of the PXS (relocate to RCS as a subsystem of RCS), then the PXS unavailability will be reduced to about 7.784E-04 or 6.82 hours per year and this is less then the allocated goal value. The major contributors to the system unavailability are mostly dominated by Stage-4 ADS valves (air piston operated valves and squib valves), inservice testing valves of ADS (solenoid operated valves), solenoid valves of Nitrogen Supply to Accumulator, and Passive Residual Heat Removal actuation valves (air operated valves). Therefore, it is recommended that those valves be analyzed more detail to gain the improvement in its reliability. It is also recommended that the fourth stage of ADS valves should be arranged according to Option-2, i.e. one 10-inch normally open motor operated gate valve in series with one 10-inch normally closed squib valve. (author). 13 refs, 3

  1. Lumbar pedicle screw placement: Using only AP plane imaging

    Directory of Open Access Journals (Sweden)

    Anil Sethi

    2012-01-01

    Conclusion: Placement of pedicle screws under fluoroscopic guidance using AP plane imaging alone with tactile guidance is safe, fast, and reliable. However, a good understanding of the radiographic landmarks is a prerequisite.

  2. A hot-spare injector for the APS linac

    International Nuclear Information System (INIS)

    Last year a second-generation SSRL-type thermionic cathode rf gun was installed in the Advanced Photon Source (APS) linac. This gun (referred to as ''gun2'') has been successfully commissioned and now serves as the main injector for the APS linac, essentially replacing the Koontz-type DC gun. To help ensure injector availability, particularly with the advent of top-up mode operation at the APS, a second thermionic-cathode rf gun will be installed in the APS linac to act as a hot-spare beam source. The hot-spare installation includes several unique design features, including a deep-orbit Panofsky-style alpha magnet. Details of the hot-spare beamline design and projected performance are presented, along with some plans for future performance upgrades

  3. The economics of medium-sized reactors in deregulated markets

    International Nuclear Information System (INIS)

    The prospects for the deployment of small and medium reactors in deregulated markets is crucially dependent on demonstrating that such reactors are economically competitive with alternative power sources. Other factors, such as safety, reliability, waste arisings, environmental impact etc are also important to get right, but unless the economics are competitive, private investment is unlikely to be available for any reactor system. This paper examines the economics of the Westinghouse AP-600, which is the only medium-sized evolutionary PWR in the world today which has achieved regulatory approval. The paper presents an economic analysis of an AP-600 which shows that medium-sized systems can be economic in a competitive market and identifies the economic barriers that need to be overcome for their deployment to become a reality. The paper shows how sensitive the overall generating cost can be to the perceived financial risk, which helps to highlight where attention most needs to be focused. (author)

  4. Reactor utilization

    International Nuclear Information System (INIS)

    In 1962, the RA reactor was operated almost three times more than in 1961, producing total of 25 555 MWh. Diagram containing comparative data about reactor operation for 1960, 1961, and 1962, percent of fuel used and U-235 burnup shows increase in reactor operation. Number of samples irradiated was 659, number of experiments done was 16. mean powered level was 5.93 MW. Fuel was added into the core twice during the reporting year. In fact the core was increased from 56 to 68 fuel channels and later to 84 fuel channels. Fuel was added to the core when the reactivity worth decreased to the minimum operation level due to burnup. In addition to this 5 central fuel channels were exchanged with fresh fuel in february for the purpose of irradiation in the VISA-2 channel

  5. Reactor Neutrinos

    CERN Document Server

    Lasserre, T; Lasserre, Thierry; Sobel, Henry W.

    2005-01-01

    We review the status and the results of reactor neutrino experiments, that toe the cutting edge of neutrino research. Short baseline experiments have provided the measurement of the reactor neutrino spectrum, and are still searching for important phenomena such as the neutrino magnetic moment. They could open the door to the measurement of coherent neutrino scattering in a near future. Middle and long baseline oscillation experiments at Chooz and KamLAND have played a relevant role in neutrino oscillation physics in the last years. It is now widely accepted that a new middle baseline disappearance reactor neutrino experiment with multiple detectors could provide a clean measurement of the last undetermined neutrino mixing angle theta13. We conclude by opening on possible use of neutrinos for Society: NonProliferation of Nuclear materials and Geophysics.

  6. Scaling of the AP600 containment large scale test facility

    International Nuclear Information System (INIS)

    The Large Scale Test (LST) Facility is an integral effects test facility which provides experimental data for validation of heat and mass transfer correlations used in WGOTHIC, the analysis code for the AP600 containment atmosphere. The LST tests consist of a series of pressurization transients in a 1/8th scale containment vessel with simulated internal heat sinks and passive containment cooling system (PCCS). These pressurization transients provide a range of transient as well as steady state data. To establish the applicability of the LST data as an integral effects facility to the AP600 containment; top-down, system-level scaling and bottom-up scaling similar to that described by Zuber (Hierarchical, Two-Tiered Scaling Methodology, 1991) were used to license the AP600 containment. Top-down, system-level scaling applied to the AP600 containment and the LST facility is the focus of this paper. Since pressure is the parameter of primary importance for the AP600 containment, the top-down, system-level scaling effort focuses on physical phenomena or processes such as heat and mass transfer. A detailed order of magnitude analysis by Spencer et al. (1997) has shown break mass-energy release, convection heat transfer, and mass transfer (condensation and evaporation) to be the dominant phenomena associated with the AP600 passive containment. To capture the aggregate influence (on pressure) of these dominant phenomena inside the AP600 containment, a simplified Rate of Pressure Change (RPC) equation is used. Variables in this equation are normalized using reference values associated with containment. The resulting coefficients in the non-dimensional RPC equation represent scaling groups which are numerically evaluated for AP600 and the LST. By comparing the magnitude of the ratios of the scaling groups for AP600 and LST, the applicability of LST data to AP600 is quantitatively assessed to judge whether the test facility is adequately scaled. Scaling ratios within the

  7. Analysis and characterization of double shell tank 241-AP-108

    International Nuclear Information System (INIS)

    This document is the first part of a three-part report describing the analysis and characterization of double shell tank 241-AP-108 which is located at the Hanford Reservation.This document is the analytical laboratory data package entitled 'Analysis and Characterization of Double Shell Tank 241-AP-108' which contains a case sampling history, the sampling protocols, the analytical procedures, sampling and analysis quality assurance and quality control measures, and chemical analysis results for samples obtained from the tank

  8. AP-102/104 Retrieval control system qualification test procedure

    Energy Technology Data Exchange (ETDEWEB)

    RIECK, C.A.

    1999-05-18

    This Qualification Test Procedure documents the results of the qualification testing that was performed on the Project W-211, ''Initial Tank Retrieval Systems,'' retrieval control system (RCS) for tanks 241-AP-102 and 241-AP-104. The results confirm that the RCS has been programmed correctly and that the two related hardware enclosures have been assembled in accordance with the design documents.

  9. The Dushak–Erekdag Survey of roAp Stars

    Indian Academy of Sciences (India)

    Tatyana Dorokhova; Nikolay Dorokhov

    2005-06-01

    The search of roAp stars at Mt. Dushak–Erekdag Observatory was started in 1992 using the 0.8m Odessa telescope equipped with a two-star high-speed photometer. We have observed more than a dozen stars so far and discovered HD 99563 as roAp star while BD+8087 is suspected to have rapid oscillations. Negative results of our observations for the search of rapid oscillations in four stars in NGC 752 are also discussed.

  10. Nuclear reactors

    International Nuclear Information System (INIS)

    A nuclear reactor has a large prompt negative temperature coefficient of reactivity. A reactor core assembly of a plurality of fluid-tight fuel elements is located within a water-filled tank. Each fuel element contains a solid homogeneous mixture of 50-79 w/o zirconium hydride, 20-50 w/o uranium and 0.5-1.5 W erbium. The uranium is not more than 20 percent enriched, and the ratio of hydrogen atoms to zirconium atoms is between 1.5:1 and 7:1. The core has a long lifetime, E.G., at least about 1200 days

  11. Nuclear reactors

    International Nuclear Information System (INIS)

    In a liquid cooled nuclear reactor, the combination is described for a single-walled vessel containing liquid coolant in which the reactor core is submerged, and a containment structure, primarily of material for shielding against radioactivity, surrounding at least the liquid-containing part of the vessel with clearance therebetween and having that surface thereof which faces the vessel make compatible with the liquid, thereby providing a leak jacket for the vessel. The structure is preferably a metal-lined concrete vault, and cooling means are provided for protecting the concrete against reaching a temperature at which damage would occur. (U.S.)

  12. 45-Day safety screening report for grab samples from Tank 241-AP-107

    International Nuclear Information System (INIS)

    Three samples; 107-AP-1C, 107-AP-2c and 107-AP-3C; were received at 222-S Laboratory for analysis of DSC, TGA and visual appearance. Four additional samples; 107-AP-1D, 107-AP-2D, 107-AP-3D and 107-AP-6; were received for visual appearance only. No results exceeded the safety screen notification criteria. This report compiles the analytical results. Tank 241-AP-107 is a double-shell tank which is not on any of the four Watch Lists

  13. Third phase formation in the extraction of Th(NO3)4 by tri-iso-amyl phosphate (TiAP) in n-tetradecane

    International Nuclear Information System (INIS)

    Studies carried out in our laboratory have shown that TiAP has high limits for third phase formation and hence suitable for the extraction of Th(IV), Pu(IV) etc. Recently the feasibility of using TiAP as an alternate extractant in fast reactor fuel reprocessing has been demonstrated in our laboratory. TiAP can also be an alternate extractant to Tri-z-butyl phosphate (TBP) for the processing of thorium based fuels and monazite phase processing. The limiting organic concentrations (LOC) and critical aqueous concentrations (CAC) for third phase formation in the extraction of Th(NO3)4 by 1.1M solutions of several trialkyl phosphates in various hydrocarbon diluents were measured in an earlier work

  14. Development of Fuel ROd Behavior Analysis code (FROBA) and its application to AP1000

    International Nuclear Information System (INIS)

    Highlights: ► A Fuel ROd Behavior Analysis code (FROBA) has been developed. ► The effects irradiation and burnup has been considered in FROBA. ► The comparison with INL’s results shows a good agreement. ► The FROBA code was applied to AP1000. ► Peak fuel temperature, gap width, hoop strain, etc. were obtained. -- Abstract: The reliable prediction of nuclear fuel rod behavior is of great importance for safety evaluation of nuclear reactors. In the present study, a thermo-mechanical coupling code FROBA (Fuel ROd Behavior Analysis) has been independently developed with consideration of irradiation and burnup effects. The thermodynamic, geometrical and mechanical behaviors have been predicted and were compared with the results obtained by Idaho National Laboratory to validate the reliability and accuracy of the FROBA code. The validated code was applied to analyze the fuel behavior of AP1000 at different burnup levels. The thermal results show that the predicted peak fuel temperature experiences three stages in the fuel lifetime. The mechanical results indicate that hoop strain at high power is greater than that at low power, which means that gap closure phenomenon will occur earlier at high power rates. The maximum cladding stress meets the requirement of yield strength limitation in the entire fuel lifetime. All results show that there are enough safety margins for fuel rod behavior of AP1000 at rated operation conditions. The FROBA code is expected to be applied to deal with more complicated fuel rod scenarios after some modifications.

  15. Approaching acquisition path analysis formally. A comparison between AP and nonAP states

    International Nuclear Information System (INIS)

    In the past, the IAEA has planned its activities mainly based on the presence of nuclear material. However, resources should be spent where they are needed most. Therefore, a new risk model was developed to change the inspection system to a comprehensive, objective‑driven approach where the State is considered as a whole, the so called State‑level concept (SLC). Acquisition path analysis (APA) is a key element of the State‑level concept. By considering the State’s nuclear profile, the APA generates a list of acquisition paths ranked by their attractiveness for the State. Currently, this process is mainly based on expert judgment. However, the IAEA’s requirements state that APA must be objective, reproducible, transparent, standardized, documented and as a result non‑discriminatory. A formal approach fulfilling the requirements was set up by the authors in the past [1]. This methodology is based on a three step approach. The process starts in the first step with the parametrization of the network. In the second step, the network is analyzed in order find all acquisition paths for a State. Finally, game theory is used in the third step to model the decisions made by the IAEA and the State. In this paper, an advanced methodology will be presented. Improvements were made in the interface definition between the three stages. Also, the general network model was updated and the automatic visualization of acquisition paths was accomplished. Furthermore, a prototype implementation will be shown. The advanced methodology was applied to two test non‑nuclear weapon States under comprehensive safeguards agreements with the IAEA. Both States hold complex fuel cycles with only small technical differences. However,only one State is supposed to have the additional protocol (AP) in force. The example will show how the presence of the AP influences the detection probabilities of illegal behavior. As a consequence, these examples also indicate where to best focus

  16. Development of thermal-hydraulic transient analysis code RETAC for AP1000 primary loop

    International Nuclear Information System (INIS)

    A thermal-hydraulic microcomputer code (RETAC, REactor Transient Analysis Code) for transient analysis of AP1000 primary loop was developed using FORTRAN language. The loss of flow accident (LOFA) was analyzed using FRTAC. Transient characteristics of some main system parameters were obtained, including the maximum fuel temperature and MDNBR in the hot channel, pressure and water level in the pressurizer and steam generator secondary side. The results show that at the early stage of the loss of flow accident, the highest fuel central temperature and MDNBR in the hot channel do not exceed specified limits and meet the safety criteria. Modular programming technique was adopted for RETAC and it is convenient for further modification and application. It is expected that the present work is instructive to develop Chinese own independent software for the design and safety analysis of large scale PWR. (authors)

  17. Nuclear reactor

    International Nuclear Information System (INIS)

    In an improved reactor core for a high conversion BWR reactor, Pu-breeding type BWR type reactor, Pu-breeding type BWR type rector, FEBR type reactor, etc., two types of fuel assemblies are loaded such that fuel assemblies using a channel box of a smaller irradiation deformation ratio are loaded in a high conversion region, while other fuel assemblies are loaded in a burner region. This enables to suppress the irradiation deformation within an allowable limit in the high conversion region where the fast neutron flux is high and the load weight from the inside of the channel box due to the pressure loss is large. At the same time, the irradiation deformation can be restricted within an allowable limit without deteriorating the neutron economy in the burner region in which fast neutron flux is low and the load weight from the inside of the channel box is small since a channel box with smaller neutron absorption cross section or reduced wall thickness is charged. As a result, it is possible to prevent structural deformations such as swelling of the channel box, bending of the entire assemblies, bending of fuel rods, etc. (K.M.)

  18. DNA cleavage at the AP site via β-elimination mediated by the AP site-binding ligands.

    Science.gov (United States)

    Abe, Yukiko S; Sasaki, Shigeki

    2016-02-15

    DNA is continuously damaged by endogenous and exogenous factors such as oxidation and alkylation. In the base excision repair pathway, the damaged nucleobases are removed by DNA N-glycosylase to form the abasic sites (AP sites). The alkylating antitumor agent exhibits cytotoxicity through the formation of the AP site. Therefore blockage or modulation of the AP site repair pathway may enhance the antitumor efficacy of DNA alkylating agents. In this study, we have examined the effects of the nucleobase-polyamine conjugated ligands (G-, A-, C- and T-ligands) on the cleavage of the AP site. The G- and A-ligands cleaved DNA at the AP site by promoting β-elimination in a non-selective manner by the G-ligand, and in a selective manner for the opposing dT by the A-ligand. These results suggest that the nucleobase-polyamine conjugate ligands may have the potential for enhancement of the cytotoxicities of the AP site. PMID:26777298

  19. State of the Art Report for Development of Control Element Drive Mechanism of the APR+ Reactor

    International Nuclear Information System (INIS)

    Recently newly-developed nuclear reactors with increased safety and enhanced performance by developed countries in the nuclear area are competing in the global nuclear market. Several reactors, for example AP600 and AP1000 by Westinghouse Electric Co. in USA, EPR by Areva in Europe, APWR by Mitsubishi Heavy Industry in Japan in the pressurized power reactor, are competing to preoccupy the nuclear market during Nuclear Renaissance. Dedicated control element drive mechanism with enhanced performance and increased safety are developed for these new reactors. And load follow capability is required, and it is estimated that load follow requirement make design requirement of a control element drive mechanism harsh. It is necessary to review the current technical state of a control element drive mechanism. This work is aimed to review the design characteristics of a past and current control element drive mechanism for a nuclear reactor and to check the direction and goal of CEDM design development recently

  20. State of the Art Report for Development of Control Element Drive Mechanism of the APR+ Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jae Seon; Choi, Suhn; Song, Chul Hwa

    2008-10-15

    Recently newly-developed nuclear reactors with increased safety and enhanced performance by developed countries in the nuclear area are competing in the global nuclear market. Several reactors, for example AP600 and AP1000 by Westinghouse Electric Co. in USA, EPR by Areva in Europe, APWR by Mitsubishi Heavy Industry in Japan in the pressurized power reactor, are competing to preoccupy the nuclear market during Nuclear Renaissance. Dedicated control element drive mechanism with enhanced performance and increased safety are developed for these new reactors. And load follow capability is required, and it is estimated that load follow requirement make design requirement of a control element drive mechanism harsh. It is necessary to review the current technical state of a control element drive mechanism. This work is aimed to review the design characteristics of a past and current control element drive mechanism for a nuclear reactor and to check the direction and goal of CEDM design development recently.

  1. We're ready if you're ready: The Westinghouse AP600 is tested and on its way to final design approval

    International Nuclear Information System (INIS)

    When its comprehensive test program was completed at the end of 1994, the Westinghouse AP600 became the most thoroughly tested advanced reactor design ever reviewed by the US Nuclear Regulatory Commission. The results of the test program have now been documented and this paper looks at the outstanding results. The AP600 test program, initiated in 1985, was a multi-discipline, multi-national effort with input from government, industry, and academic organizations. The success of the test program, long a major focus of Westinghouse and NRC discussions about AP600, puts the design of this advanced reactor systems well on its way to final design approval which is expected by the end of 1996. While the NRC's review of the test program data is still being completed, the Commission has acknowledged the simplicity and safety of the design. In addition to providing fundamental engineering data to support the licensing process leading to NRC design certification, the test program imbues potential utility owners with confidence in the innovative aspects of the AP600

  2. An alternatively spliced mRNA from the AP-2 gene encodes a negative regulator of transcriptional activation by AP-2.

    OpenAIRE

    Buettner, R; Kannan, P; Imhof, A.; Bauer, R.; Yim, S O; Glockshuber, R; Van Dyke, M W; Tainsky, M A

    1993-01-01

    AP-2 is a retinoic acid-inducible and developmentally regulated activator of transcription. We have cloned an alternative AP-2 transcript (AP-2B) from the human teratocarcinoma cell line PA-1, which encodes a protein differing in the C terminus from the previously isolated AP-2 protein (AP-2A). This protein contains the activation domain of AP-2 and part of the DNA binding domain but lacks the dimerization domain which is necessary for DNA binding. Analysis of overlapping genomic clones spann...

  3. Importance of the multi-modules study in PSA; Importancia del estudio de multi-modulos en APS

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez R, V. J.; Nelson E, P. F., E-mail: judith_gonzalez_rodriguez@outlook.es [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)

    2015-09-15

    The current approach that has taken the Probabilistic Safety Analysis (PSA) consists of doing all the APS analysis including the existence of multi-units in the nuclear power plants (NPP), this new approach seeks to analyze the risk of site, evaluating all reactors together. The main reasons for this trend are: the accident occurred on March 2011 in Fukushima Daiichi in Japan, with serious consequences in more than one reactor of the NPP and the current planning and construction of new Small Modular Reactors, which host more than one module on the same NPP and are connected to a single control room. This study analyzes how to model the risk of a multi-module NPP. In 2013, the ASME/ANS standard for advanced reactors that are not light-water reactors was published, in which the requirements to realize a PSA including multi-units or modules are shown; however, does not describe the methodology to do that. This article presents a methodology to calculate the risk of the site in a PBMR plant with two modules. This methodology consists of two models of trees of different events, one that evaluates to a single PBMR module and another that evaluates the two modules together. Both models are responsible to show their differences and compare results to finally demonstrate the need for new methodologies for risk analysis site in multi-modules and units. (Author)

  4. AP@home: The Artificial Pancreas Is Now at Home.

    Science.gov (United States)

    Heinemann, Lutz; Benesch, Carsten; DeVries, J Hans

    2016-07-01

    In the past years the development of an artificial pancreas (AP) has made great progress and many activities are ongoing in this area of research. The major step forward made in the last years was moving the evaluation of AP systems from highly controlled experimental conditions to daily life conditions at the home of patients with diabetes; this was also the aim of the European Union-funded AP@home project. Over a time period of 5 years a series of clinical studies were performed that culminated in 2 "final studies" during which an AP system was used by patients in their home environment for 2 or 3 months without supervision by a physician, living their normal lives. Two different versions of the AP system developed within this project were evaluated. A significant improvement in glycated hemoglobin was observed during closed-loop conditions despite the fact that during the control period the patients used the best currently available therapeutic option. In addition, a "single-port AP system" was developed within the project that combines continuous glucose monitoring and insulin infusion at a single tissue site. By using such a combined device the patients not only have to carry one less device around, the number of access points through the skin is also reduced from 2 to 1. In summary, close cooperation of 12 European partners, both academic centers and industry, enabled the development and evaluation of AP systems under daily life conditions. The next step is to develop these into products in cooperation with commercial partners. PMID:26888971

  5. The AP1000 registered philosophy fits nuclear new build in Central Europe

    International Nuclear Information System (INIS)

    The World Nuclear Association estimates a steady growth in the number of reactors to be built in the next 20 years. The number of reactors in operation worldwide today is about 440 and will rise within the next couple of decades. It is speculated that Western Europe (including Germany) will have more reactors coming offline than online in the future due to limited lifetime versus plans for new build. In contrast, Eastern Europe (including Russia) is forecasting an increase in their nuclear generating capacity. This includes new market entrants such as Poland as well as expansion projects in the Czech Republic and Hungary; Germany's eastern neighbors. Unfortunately, as Germany and Switzerland phase out nuclear the net capacity in Western Europe is expected to drop even more. In addition to the phase out of nuclear, the federal German government decided to increase the power generation of renewables, focusing on wind and solar. The consequence of simultaneously implementing these new requirements is the creation of high frequency load changes from wind fluctuations or solar peaks without having the nuclear base load to maintain a constant capacity. These decisions on Germany's energy polices has extenuating circumstances which create challenges for local transmission system operators, as well as for neighboring countries' transmission system operators due to the synchronous grid of Continental Europe. This challenge will force the countries connected to Germany by the synchronous grid to place even more importance on their nuclear new build programs in the years to come. Though Germany is phasing out nuclear all together, its neighboring countries in Central and Eastern Europe are continuing with nuclear new build efforts. Therefore, it is still important for the German public to understand the options the nuclear industry have when selecting nuclear reactor vendors. The designs of today are more technically advanced, however the AP1000 registered plant stands out

  6. Using accident management to address phenomenological uncertainties related to lower plenum debris bed chemistry and mixing during in-vessel retention (IVR) of molten core debris in the AP1000 passive plant

    International Nuclear Information System (INIS)

    In-vessel retention (IVR) of core debris via external reactor vessel cooling is an important severe accident management strategy that is inherent in the AP1000 passive nuclear power plant. Uncertainties in molten debris bed chemistry and mixing behavior in the lower plenum of a RPV (reactor pressure vessel), at the extreme bounding limits, have been suggested to potentially result in lower plenum debris bed configurations that may challenge vessel integrity during IVR. To resolve epistemic uncertainties related to severe accident phenomena, the uncertainties are addressed via engineered severe accident management solutions that are shown to be reliable using a probabilistic framework to quantify success. Vessel failure probability and large release frequency in the AP1000 plant design are demonstrated to be as low as reasonably practicable (ALARP), and the IVR strategy is demonstrated to provide a robust approach to severe accident management in the AP1000 plant, capable of addressing postulated uncertainties and concerns

  7. Reactor container

    International Nuclear Information System (INIS)

    A reactor container has a suppression chamber partitioned by concrete side walls, a reactor pedestal and a diaphragm floor. A plurality of partitioning walls are disposed in circumferential direction each at an interval inside the suppression chamber, so that independent chambers in a state being divided into plurality are formed inside the suppression chamber. The partition walls are formed from the bottom portion of the suppression chamber up to the diaphragm floor to isolate pool water in a divided state. Operation platforms are formed above the suppression chamber and connected to an access port. Upon conducting maintenance, inspection or repairing, a pump is disposed in the independent chamber to transfer pool water therein to one or a plurality of other independent chambers to make it vacant. (I.N.)

  8. Reactor building

    International Nuclear Information System (INIS)

    The present invention concerns a structure of ABWR-type reactor buildings, which can increase the capacity of a spent fuel storage area at a low cost and improved earthquake proofness. In the reactor building, the floor of a spent fuel pool is made flat, and a depth of the pool water satisfying requirement for shielding is ensured. In addition, a depth of pool water is also maintained for a equipment provisionally storing pool for storing spent fuels, and a capacity for a spent fuel storage area is increased by utilizing surplus space of the equipment provisionally storing pool. Since the flattened floor of the spent fuel pool is flushed with the floor of the equipment provisionally storing pool, transfer of horizontal loads applied to the building upon occurrence of earthquakes is made smooth, to improve earthquake proofness of the building. (T.M.)

  9. Nuclear reactors

    International Nuclear Information System (INIS)

    Disclosed is a nuclear reactor cooled by a freezable liquid has a vessel for containing said liquid and comprising a structure shaped as a container, and cooling means in the region of the surface of said structure for effecting freezing of said liquid coolant at and for a finite distance from said surface for providing a layer of frozen coolant on and supported by said surface for containing said liquid coolant. In a specific example, where the reactor is sodium-cooled, the said structure is a metal-lined concrete vault, cooling is effected by closed cooling loops containing NaK, the loops extending over the lined surface of the concrete vault with outward and reverse pipe runs of each loop separated by thermal insulation, and air is flowed through cooling pipes embedded in the concrete behind the metal lining. 7 claims, 3 figures

  10. Studies on extraction behavior of U(VI) and Th(IV) from nitric acid medium using tri-iso-amyl phosphate (TiAP)/ n-dodecane as extractant

    International Nuclear Information System (INIS)

    Tri-iso-amyl phosphate is a higher homologue of TBP, retaining many advantages of TBP while eliminating or mitigating its disadvantages. Its longer, branched alkyl chain, resists third phase formation during overloading of actinides. The TiAP is being considered as an alternative of TBP for the reprocessing of Fast Breeder Reactor fuels due to its various advantages over TBP

  11. Past, Present, and Future of AP Chemistry: A Brief History of Course and Exam Alignment Efforts

    Science.gov (United States)

    Magrogan, Serena

    2014-01-01

    As part of the Advanced Placement (AP) Program's commitment to continually enhance alignment with current best practices in college-level learning, the AP Program is currently evaluating and redesigning courses and exams, one of which launched during the 2013-2014 academic school year: AP chemistry. The history of the AP chemistry course and…

  12. AP Report to the Nation: A Closer Look at the Nation and Florida

    Science.gov (United States)

    Sawtell, Ellen A.; Gillie, Jacqueline M.; Smith, Patricia Z.

    2012-01-01

    In February 2012, the College Board published The 8th Annual AP Report to the Nation. This session provides a deeper dive into key information for the United States with an emphasis on Florida, and participants hear how one school in Florida utilizes AP Potential™ to help build their AP Program. Participants also learn about AP participation and…

  13. NEUTRONIC REACTORS

    Science.gov (United States)

    Anderson, J.B.

    1960-01-01

    A reactor is described which comprises a tank, a plurality of coaxial steel sleeves in the tank, a mass of water in the tank, and wire grids in abutting relationship within a plurality of elongated parallel channels within the steel sleeves, the wire being provided with a plurality of bends in the same plane forming adjacent parallel sections between bends, and the sections of adjacent grids being normally disposed relative to each other.

  14. Nuclear reactor

    International Nuclear Information System (INIS)

    The liquid metal (sodium) cooled fast breeder reactor has got fuel subassemblies which are bundled and enclosed by a common can. In order to reduce bending of the sides of the can because of the load caused by the coolant pressure the can has got a dodecagon-shaped crosssection. The surfaces of the can may be of equal width. One out of two surfaces may also be convex towards the center. (RW)

  15. Full core simulation of Loss of Coolant transients in an AP600 reactor using COBRA

    International Nuclear Information System (INIS)

    Core transients have been calculated with full core and single channel models by COBRA-IV-I and with single channel model by RELAPS/MOD2. From the single channel simulations, it has been found that for transients where the rate of change of the conditions is moderate to rapid, like in a small LOCA, there is an excellent agreement between the results of the two codes. For rapid transients as , in a large LOCA the. agreement is less favorable, although qualitatively similar results are obtained. Result obtained when using the more accurate full core model are generally different than that obtained when a SC model is used. Full core simulation indicates that the coolant which enters the core after the blowout flows mainly through the.cooler channels and bypasses the hot channels cools them only by heat conduction. This kind of simulation is essential for calculation and verification of the hot channel factor. (authors); 6 refs., 5 figs

  16. Nuclear reactor

    International Nuclear Information System (INIS)

    A detector having high sensitivity to fast neutrons and having low sensitivity to thermal neutrons is disposed for reducing influences of neutron detector signals on detection values of neutron fluxes when the upper end of control rod pass in the vicinity of the neutron flux detector. Namely, the change of the neutron fluxes is greater in the thermal neutron energy region while it is smaller in the fast neutron energy region. This is because the neutron absorbing cross section of B-10 used as neutron absorbers of control rods is greater in the thermal neutron region and it is smaller in the fast neutron region. As a result, increase of the neutron detection signals along with the local neutron flux change can be reduced, and detection signals corresponding to the reactor power can be obtained. Even when gang withdrawal of operating a plurality of control rods at the same time is performed, the reactor operation cycle can be measured accurately, thereby enabling to shorten the reactor startup time. (N.H.)

  17. Containment integrity analysis for the Westinghouse Advanced AP600

    International Nuclear Information System (INIS)

    Since 1987, Westinghouse has been performing containment cooling analyses in support of the advanced AP600 plant design. This analysis effort was intended to verify the feasibility of the passive containment cooling system (PCCS) features of the AP600 design, which is being jointly developed by Westinghouse, Burns and Roe Company, and Avondale Industries. To support this goal, the response of the AP600 containment has been analyzed for a large-break loss-of-coolant-accident (LOCA) and for a large steam line break (SLB). These cases were chosen based on the characteristic mass and energy releases each scenario would impose on the containment, with LOCA releases taxing the long-term heat-removal aspects while the SLB release typically defines the limiting short-term response. The transient results indicate that the PCCS design is feasible and capable of removing sufficient heat to limit containment pressure to within acceptable limits

  18. Experience with the EPICS PV Gateway at the APS

    CERN Document Server

    Evans, Kenneth

    2005-01-01

    The EPICS PV Gateway has become a stable, high-performance application that provides access to process variables while minimizing the impact on critical IOCs and implementing additional access security. The additional access security typically prevents write access but is highly configurable. The Advanced Photon Source (APS) currently uses 40 Gateways running on 11 machines to provide access to the machine network from the offices and for the individual experimental teams. These include reverse Gateways that allow administration of all 40 APS Gateways from a single MEDM screen, even though the Gateways are running on separate networks. This administration includes starting, stopping, making and viewing reports, and viewing and editing access security files. There is one Gateway that provides process variable renaming. This paper provides an overview of the Gateways at the APS and describes the procedures that have been set up to use and administer them.

  19. PKA-activated ApAF–ApC/EBP heterodimer is a key downstream effector of ApCREB and is necessary and sufficient for the consolidation of long-term facilitation

    OpenAIRE

    LEE, Jin-A; Lee, Sue-Hyun; Lee, Changhoon; Chang, Deok-Jin; Lee, Yong; Kim, Hyoung; Cheang, Ye-Hwang; Ko, Hyoung-Gon; Lee, Yong-Seok; Jun, Heejung; Bartsch, Dusan; Kandel, Eric R.; Kaang, Bong-Kiun

    2006-01-01

    Long-term memory requires transcriptional regulation by a combination of positive and negative transcription factors. Aplysia activating factor (ApAF) is known to be a positive transcription factor that forms heterodimers with ApC/EBP and ApCREB2. How these heterodimers are regulated and how they participate in the consolidation of long-term facilitation (LTF) has not, however, been characterized. We found that the functional activation of ApAF required phosphorylation of ApAF by PKA on Ser-2...

  20. Autosomal recessive spastic tetraplegia caused by AP4M1 and AP4B1 gene mutation: expansion of the facial and neuroimaging features.

    Science.gov (United States)

    Tüysüz, Beyhan; Bilguvar, Kaya; Koçer, Naci; Yalçınkaya, Cengiz; Çağlayan, Okay; Gül, Ece; Sahin, Sezgin; Çomu, Sinan; Günel, Murat

    2014-07-01

    Adaptor protein complex-4 (AP4) is a component of intracellular transportation of proteins, which is thought to have a unique role in neurons. Recently, mutations affecting all four subunits of AP4 (AP4M1, AP4E1, AP4S1, and AP4B1) have been found to cause similar autosomal recessive phenotype consisting of tetraplegic cerebral palsy and intellectual disability. The aim of this study was analyzing AP4 genes in three new families with this phenotype, and discussing their clinical findings with an emphasis on neuroimaging and facial features. Using homozygosity mapping followed by whole-exome sequencing, we identified two novel homozygous mutations in AP4M1 and a homozygous deletion in AP4B1 in three pairs of siblings. Spastic tetraplegia, microcephaly, severe intellectual disability, limited speech, and stereotypic laughter were common findings in our patients. All patients also had similar facial features consisting of coarse and hypotonic face, bitemporal narrowing, bulbous nose with broad nasal ridge, and short philtrum which were not described in patients with AP4M1 and AP4B1 mutations previously. The patients presented here and previously with AP4M1, AP4B1, and AP4E1 mutations shared brain abnormalities including asymmetrical ventriculomegaly, thin splenium of the corpus callosum, and reduced white matter volume. The patients also had hippocampal globoid formation and thin hippocampus. In conclusion, disorders due to mutations in AP4 complex have similar neurological, facial, and cranial imaging findings. Thus, these four genes encoding AP4 subunits should be screened in patients with autosomal recessive spastic tetraplegic cerebral palsy, severe intellectual disability, and stereotypic laughter, especially with the described facial and cranial MRI features. PMID:24700674

  1. Transcriptional Regulation of the AP-2α Promoter by BTEB-1 and AP-2rep, a Novel wt-1/egr-Related Zinc Finger Repressor

    OpenAIRE

    Imhof, Axel; Schuierer, Marion; Werner, Oliver; Moser, Markus; Roth, Christina; Bauer, Reinhard; BUETTNER, REINHARD

    1999-01-01

    AP-2 transcription factors have been suggested to exert key regulatory functions in vertebrate embryonic development, in tumorigenicity of various cancer cell types, and in controlling cell cycle and apoptotic effector genes. In this study, we investigated transcriptional regulation of the AP-2α gene promoter mediated by an autoregulatory element (referred to as A32) with a core consensus AP-2 binding site at position −336 relative to the mRNA initiation site. AP-2 and multiple different nucl...

  2. Concepts for the reactor safety systems for the new nuclear power project in the Republic of Bulgaria

    International Nuclear Information System (INIS)

    Discussed are two main proposals for the construction of new nuclear power plant at the site of the Kozloduy NPP in Bulgaria: AES-92 VVER-1000 designed and produced for Belene NPP, and alternative with a new reactor or VVER-1200 (AES-2006) developed by Rosatom, or reactor AP1000 designed by Westinghouse. Attention is paid to the basic principles underlying the design of passive and specific protective equipment that significantly increased the reactor safety

  3. Reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    In a BWR type nuclear reactor, the number of first fuel assemblies (uranium) loaded in a reactor core is smaller than that of second fuel assemblies (mixed oxide), the average burnup degree upon take-out of the first fuel assemblies is reduced to less than that of the second fuel assemblies, and the number of the kinds of the fuel rods constituting the first fuel assemblies is made smaller than that of the fuel rods constituting the second fuel assemblies. As a result, the variety of the plutonium enrichment degree is reduced to make the distribution of the axial enrichment degree uniform, thereby enabling to simplify the distribution of the enrichment degree. Then the number of molding fabrication steps for MOX fuel assemblies can be reduced, thereby enabling to reduce the cost for molding and fabrication. (N.H.)

  4. Analysis of the planning and scheduling functionality in APS systems

    Science.gov (United States)

    Steger-Jensen, Kenn; Hvolby, Hans-Henrik

    2001-10-01

    The paper discusses the basic functionality of planning and scheduling in Advanced Planning and Scheduling systems (APS). Three basic planning options - unconstrained planning, constrained planning and optimization are analyzed by use of theory and examples based on test of an APS system. Even though the planning functionality are radically improved compared to MRP and MRP II, the balance between the objectives are found to be too rigid. This conclusion is based on a number of examples, comparing the outcome of different objectives such as constraints based planning versus optimized planning.

  5. SN 2002ap, the hypernova of class Ic

    OpenAIRE

    Pandey, S. B.; Sahu, D. K.; Anupama, G. C.; Bhattacharya, D; Sagar, Ram

    2003-01-01

    The supernova SN 2002ap was discovered in the outer regions of the nearby spiral M74 on January 29.4 UT. Early photometric and spectroscopic observations indicate the supernova belongs to the class of Ic hypernova. Late time (After JD 2452500) light curve decay slopes are similar to that of the hypernovae SN 1997ef and SN 1998bw. We present here the $BVRI$ photometric light curves and colour evolutions of SN 2002ap to investigate the late time nature of the light curve.

  6. Status of the Advanced Photon Source (APS) linear accelerator

    International Nuclear Information System (INIS)

    A 2856-MHz S-band, electron-positron linear accelerator (linac) has been constructed at the Advanced Photon Source (APS). It is the source of particles and the injector for the other APS accelerators, and linac commissioning is well underway. The linac is operated 24 hours per day to support linac beam studies and rf conditioning, as well as positron accumulator ring and synchrotron commissioning studies. The design goal for accelerated positron current is 8-mA, and has been met. Maximum positron energy to date is 420-MeV, approaching the design goal of 450-MeV. The linac design and its performance are discussed

  7. Miniature Autonomous Star Tracker Based on CMOS APS

    OpenAIRE

    Ying, Dong; Zheng, You; Fei, Xing; Qin, Chou

    2006-01-01

    An APS (Active Pixel Sensor) based autonomous star tracker (AAST) has been proposed for small satellite and microsatellite attitude determination. A prototype of AAST has been developed. It has low mass of 1kg, low power of 3W, high rate up to 5Hz, and acquisition success rate of higher than 99.9%. The improvements in dimensions and performances are realized with the replacement of the CCD (Charge Coupled Device) by the APS. The optical design of the prototype is based on PSF (Point Spread Fu...

  8. AP600 Rod Ejection Accident Analysis Under Low Power Operating Mode

    International Nuclear Information System (INIS)

    AP600 is one of PWRs type reactors being developed by Westinghouse. It was designed to have a Rapid Power Reduction System (RPRS) in its Operating and Control System which enable it to operate under low power level condition, i.e. below 50% of rated power, following a great load rejection (>50%). with this feature, it is important to conduct some safety analysis for this low power operating condition, the same as those normally imposed to the normal power operating condition including the case of Rod Ejection Accident. This paper presents the result of analysis relating with the Rod Ejection case under low power operating mode (RPRS is in operation), as part of preliminary studies for the feasibility of the implementation of the RPRS. There are two main points to be investigated in this analysis i.e., the fuel integrity and the Shutdown Capability of the available control rods. This was performed through the observation of the Maximum Linear Power (MLP) arised following Rod Ejection event and through the Subcriticality test. The results indicate that the resulted MLP was still far below the maximum design limit for transient conditions, assuring the fuel integrity and the available rods could still bring the reactor to subcritical condition following the Rod Ejection event

  9. The conceptual design of IPR1000 reactor pressure vessel for PWR type

    International Nuclear Information System (INIS)

    The conceptual design of IPR1000 reactor pressure vessel for PWR type has been configured, material selection and dimension parameter are designed to cover the reactor cooling system (RCS), nuclear fuel assembly, and others internals reactor. The reactor pressure vessel consist of closure head assembly, vessel shell upper head assembly, vessel shell lower assembly, and inlet and outlet nozzle. These are designed capable to support weight of RPV, at pressures and temperature of each 2485 psig and 650 °F. The design refers to AP1000 as according to ASME code and industrials standard applicable for Nuclear Power Plants (NPP). (author)

  10. Passive cooling systems in power reactors

    International Nuclear Information System (INIS)

    This paper reviews several R and D activities associated with the subject of passive cooling systems, conducted by the N.R.C.Negev thermohydraulic group. A short introduction considering different types of thermosyphons and their applications is followed by a detailed description of the experimental work, its results and conclusions. An ongoing research project is focused on the evaluation of the external dry air passive containment cooling system (PCCS) in the AP-600 (Westinghouse advanced pressurized water reactor). In this context some preliminary theoretical results and planned experimental research are for the fature described

  11. Types of Nuclear Reactors

    International Nuclear Information System (INIS)

    The presentation is based on the following areas: Types of Nuclear Reactors, coolant, moderator, neutron spectrum, fuel type, pressurized water reactor (PWR), boiling water reactor (BWR) reactor pressurized heavy water (PHWR), gas-cooled reactor, RBMK , Nuclear Electricity Generation,Challenges in Nuclear Technology Deployment,EPR, APR1400, A P 1000, A PWR, ATMEA 1, VVER-1000, A PWR, VVER 1200, Boiling Water Reactor, A BWR, A BWR -II, ESBUR, Ke ren, AREVA, Heavy Water Reactor, Candu 6, Acr-1000, HWR, Bw, Iris, CAREM NuCcale, Smart, KLT-HOS, Westinghouse small modular Reactor, Gas Cooled Reactors, PBMR.

  12. Analysis of Large Release Source Terms in AP1000 Nuclear Power Plant%AP1000核电厂大量放射性释放源项分析

    Institute of Scientific and Technical Information of China (English)

    张琨

    2012-01-01

    AP1000核电厂的某些严重事故情景中,安全壳可能发生失效或旁通,导致大量放射性物质释放到环境中,造成严重的放射性污染.针对大量放射性释放频率贡献最大的3种释放类别(安全壳旁通、安全壳早期失效和安全壳隔离失效),分别选取典型的严重事故序列(蒸汽发生器传热管破裂、自动卸压系统阀门误开启和压力容器破裂),使用MAAP程序计算分析了释放到环境中的裂变产物源项.该分析结果为量化AP1000核电厂的放射性释放后果和厂外剂量分析提供了必要的输入.%In some severe accident scenarios of AP1000 nuclear power plant, a breach or bypass of the containment will lead to large release to environment, which causes severe radioactive pollution of environment. Three release categories (bypass, early containment failure and containment isolation failure) have the largest contribution to large release frequency. Three typical severe accidents (steam generator tube rupture, spuriously open of automatic depressurization system valves and reactor pressure vessel rupture) were selected as typical cases corresponding to the three release categories and the fission-product source terms released to environment were calculated using MAAP code. The analysis results are provided as essential input data for quantifying the release of AP1000 nuclear power plant and the offsite dose analysis.

  13. Nuclear reactor

    International Nuclear Information System (INIS)

    A nuclear reactor is described in which the core components, including fuel-rod assemblies, control-rod assemblies, fertile rod-assemblies, and removable shielding assemblies, are supported by a plurality of separate inlet modular units. These units are referred to as inlet module units to distinguish them from the modules of the upper internals of the reactor. The modular units are supported, each removable independently of the others, in liners in the supporting structure for the lower internals of the reactor. The core assemblies are removably supported in integral receptacles or sockets of the modular units. The liners, units, sockets and assemblies have inlet openings for entry of the fluid. The modular units are each removably mounted in the liners with fluid seals interposed between the opening in the liner and inlet module into which the fluid enters in the upper and lower portion of the liner. Each assembly is similarly mounted in a corresponding receptacle with fluid seals interposed between the openings where the fluid enters in the lower portion of the receptacle or fitting closely in these regions. As fluid flows along each core assembly a pressure drop is produced along the fluid so that the fluid which emerges from each core assembly is at a lower pressure than the fluid which enters the core assembly. However because of the seals interposed in the mountings of the units and assemblies the pressures above and below the units and assemblies are balanced and the units are held in the liners and the assemblies are held in the receptacles by their weights as they have a higher specific gravity than the fluid. The low-pressure spaces between each module and its liner and between each core assembly and its module is vented to the low-pressure regions of the vessel to assure that fluid which leaks through the seals does not accumulate and destroy the hydraulic balance

  14. Berberine inhibits cyclin D1 expression via suppressed binding of AP-1 transcription factors to CCND1 AP-1 motif

    Institute of Scientific and Technical Information of China (English)

    Ye LUO; Yu HAO; Tai-ping SHI; Wei-wei DENG; Na LI

    2008-01-01

    Aim: To verify the suppressive effect of berberine on the proliferation of the human pulmonary giant cell carcinoma cell line PG and to demonstrate the mecha-nisms behind the antitumoral effects of berberine. Methods: The proliferative effects of PG cells were detected by 3-(4,5-dimethylthiazol-2-yl)-2,5-diphenyltetrazolium bromide colorimetry. The cell cycle was examined by flow cytometry. The expression level of cyclin D1 was detected by RT-PCR. The activities of the activating protein-1 (AP-1) and NF-κB signaling pathways related to cyclin D1 were examined by luciferase assay. The cytoplasmic level of c-Jun was detected by Western blot analysis. An electrophoretic mobility shift assay was used to examiae the binding of transcription factors to the cyclin D1 gene (CCNDl) AP-1 motif. Results: The results showed that the proliferation of PG cells treated with different concentrations (10, 20, and 40 μg/mL) of berberine for 24 and 48 h was suppressed significantly compared to the control group. After treatment with berberine, the proportion of PG cells at the G0/G1 phase increased, while cells at the S and G2/M phases decreased. Berberine could inhibit the expression of cyclin D1 in PG cells. Berberine inhibited the activity of the AP-1 signaling pathway, but had no significant effect on the NF-κB signaling pathway. Berberine suppressed the expression of c-Jun and decreased the binding of tran-scription factors to the CCND1 AP-1 motif. Conclusion: Berberine suppresses the activity of the AP-1 signaling pathway and decreases the binding of transcrip-tion factors to the CCND1 AP-1 motif. This is one of the important mechanisms behind the antitumoral effects of berberine as a regulator of cyclin D1.

  15. Nuclear research reactors

    International Nuclear Information System (INIS)

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

  16. Nuclear reactor physics course for reactor operators

    International Nuclear Information System (INIS)

    The education and training of nuclear reactor operators is important to guarantee the safe operation of present and future nuclear reactors. Therefore, a course on basic 'Nuclear reactor physics' in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The aim of the basic course on 'Nuclear Reactor Physics for reactor operators' is to provide the reactor operators with a basic understanding of the main concepts relevant to nuclear reactors. Seen the education level of the participants, mathematical derivations are simplified and reduced to a minimum, but not completely eliminated

  17. Safety and economics of new generations of nuclear reactors

    International Nuclear Information System (INIS)

    In the framework of the so-called ENGINE program (ENergy Generation In the Natural Environment) of ECN, safety and economic aspects of nuclear reactor generations have been reviewed. After the Chernobyl accident in 1986 much has been done to enhance the safety of nuclear reactors. One promising development is the so-called passively safe light water reactor, which can be considered as the next generation of light water reactors. It has a rated power of 600 MWe or less, and safety is primarily based on passive systems. In accident conditions there is no need for operator action to keep the core cooled and covered with water for at least 72 hours. Passively safe water reactors need no demonstration stage and could be commercial around 1995. Two nuclear reactors of current design (1st generation, APWR and ABWR) and 3 pas-sively safe reactors (2nd generation, AP600, SBWR and SIR) are reviewed. Besides the 2nd generation reactors, other reactor types come into con-sideration, which are characterized by the most consequent utilisation of passive safety. A core melt accident with such a reactor is either highly unlikely or virtually impossible. Because of their advanced design demonstration is inevitable. Two reactor types of this 3rd generation are reviewed. Commercial introduction is expected after 2005. The economics of nuclear reactors are compared to those of ad-vanced coal fired power plants for the period 2000-2045. The Integrated Coal Gasification Combined Cycle (IGCC) plant is used as a reference, and economically acceptable nuclear investment costs are calculated, based on annualised costs and a 30 year economic life. These economi-cally acceptable investment costs are compared to published investment costs of current reactors. (author). 113 refs.; 7 figs.; 22 tabs

  18. Intermediate-break LOCA analyses for the AP600 design

    International Nuclear Information System (INIS)

    A postulated double-ended guillotine break of a direct-vessel-injection line in an AP600 plant has been analyzed. This event is characterized as an intermediate break loss-of-coolant accident (IBLOCA). Most of the insights regarding the response of the AP600 safety systems to the postulated accident are derived from calculations performed with the TRAC-PFl/MOD2 code. However, complementary insights derived from a scaled experiment conducted in the ROSA facility, as well as insights based upon calculations by other codes, are also presented. The key processes occurring in an AP600 during a IBLOCA are primary coolant system depressurization, inventory depletion, inventory replacement via emergency core coolant injection, continuous core cooling, and long-term decay heat rejection to the atmosphere. Based upon the calculated and experimental results, the AP600 will not experience a core heat up and will reach a safe shutdown state using only safety-class equipment. Only the early part of the long-term cooling period initiated by In-containment Refueling Water Storage Tank injection was evaluated Thus, the observation that the core is continuously cooled should be verified for the latter phase of the long-term cooling period, the interval when sump injection and containment cooling processes are important

  19. Tank 241-AP-106 tank characterization plan: Revision 1

    International Nuclear Information System (INIS)

    Tank 241-AP-106 (AP-106) is a candidate feed tank which is expected to be processed at the 242-A Evaporator. Three issues related to the overall concern of the evaporator must be evaluated: compatibility of the candidate waste with respect to feed tank, slurry tank, and evaporator requirements; safety parameters of the candidate waste tank to avoid a facility condition which is outside the safety boundaries; and compliance of the waste as dictated by regulations from various government and environmental agencies. The characterization efforts of this Tank Characterization Plan are focused on the resolution of the issues above. To evaluate the potential for waste incompatibility with the feed tank, slurry tank, and evaporator, as well as relevant safety issues, analyses will be performed on the grab samples obtained from tank AP-106. These analyses are discussed in Section 4.0. Once the characterization of tank AP-106 has been performed, the waste compatibility and safety assessment shall be conducted. This effort is discussed elsewhere

  20. Time Trials--An AP Physics Challenge Lab

    Science.gov (United States)

    Jones, David

    2009-01-01

    I have come to the conclusion that for high school physics classroom and laboratory experiences, simpler is better! In this paper I describe a very simple and effective lab experience that my AP students have thoroughly enjoyed year after year. I call this lab exercise "Time Trials." The experiment is simple in design and it is a lot of fun for…

  1. The AP Lever for Boosting Access, Success, and Equity

    Science.gov (United States)

    Roegman, Rachel; Hatch, Thomas

    2016-01-01

    Four New Jersey school districts worked together to increase student achievement by applying a number of strategies focused on getting traditionally underrepresented students to take more AP courses. The districts are members of the New Jersey Network of Superintendents (NJNS), comprising 15 superintendents who work together to develop systemwide…

  2. The New AP Chemistry Exam: Its Rationale, Content, and Scoring

    Science.gov (United States)

    Price, Paul D.; Kugel, Roger W.

    2014-01-01

    The 2013-2014 academic year marks the rollout of the redesigned advanced placement (AP) chemistry course and exam. There have been many questions as to why the course was redesigned and how the new examination will differ from its legacy version. In this article we give a brief overview of the legacy course and examine why a redesign occurred in…

  3. Early Telegraphic News Dispatches: The Forerunner of the AP.

    Science.gov (United States)

    Schwarzlose, Richard A.

    The origin of the Associated Press (AP) lies in the early cooperative news gathering efforts of the editors of several New York newspapers. As early as May 1846, these editors were "pooling" their energies in response to newly developed modes of communication--the wire and wireless telegraph and the trans-oceanic steamship mail services. The…

  4. Integrating Particulate Representations into AP Chemistry and Introductory Chemistry Courses

    Science.gov (United States)

    Prilliman, Stephen G.

    2014-01-01

    The College Board's recently revised curriculum for advanced placement (AP) chemistry places a strong emphasis on conceptual understanding, including representations of particle phenomena. This change in emphasis is informed by years of research showing that students could perform algorithmic calculations but not explain those calculations…

  5. A process definition repository based on step AP 213

    Energy Technology Data Exchange (ETDEWEB)

    Butler, J.W.

    1997-09-01

    Over the years, in the context of numerically controlled machined part manufacturing, the loss, misinterpretation, and redundancy of re-inputting manufacturing instructions and data during the evolution of a product design into the finished product has been a resource depleting and costly endeavor. It is the intent of this project to utilize the emerging standards from the International Standards Organization, ISO 10303 Standard for the Exchange of Product Model Data, commonly referred to as STEP, to store and retrieve process planning information for a set of production work instructions. The project focuses on the utilization of the 1995 version of the Draft International Standard ISO/DIS 10303-213:1995 (E) Application protocol: Numerical control process plans for machined parts (AP213). This project illustrates the methodologies used to build an object-oriented Process Definition Repository (PDR), describes both the benefits and shortcomings experienced in implementing AP213, and recommends enhancements to AP213 for process planning information. The deliverable will be a Part 21 data file, based on the application-interpreted model for AP213 and integrated with product design data.

  6. 76 FR 82079 - AP1000 Design Certification Amendment

    Science.gov (United States)

    2011-12-30

    ... Vessel (RPV) Support System. SFP Decay Heat Analysis and Associated Design Changes. Spent Fuel Rack... any person. The NRC originally approved the AP1000 design certification in a final rule in 2006 (71 FR... notice of acceptance (ADAMS Accession No. ML073600743) in the Federal Register (73 FR 4926; January...

  7. Tank 241AP104 Grab Sampling and Analysis Plan

    Energy Technology Data Exchange (ETDEWEB)

    TEMPLETON, A.M.

    2000-11-09

    This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for samples obtained from tank 241-AP-104. The purpose of this sampling event is to obtain information about the characteristics of the contents of 241-AP-104 required to provide sample material to the Waste Treatment Contractor. Grab samples will be obtained from riser 001 to provide sufficient material for the chemical analyses and tests required to satisfy these data quality objectives and ICD-23. The 222-S Laboratory will receive samples; composite the samples; perform chemical analyses on composite samples; and provide samples to the Waste Treatment Contractor and the Process Chemistry Laboratory. The Process Chemistry Laboratory at the 222-S Laboratory Complex will perform process tests to evaluate the behavior of the 241-AP-104 waste undergoing the retrieval and treatment scenarios defined in the applicable DQOs. The Waste Treatment Contractor will perform process verification and waste form qualification tests. Requirements for analyses of samples originating in the L & H DQO process tests will be documented in the corresponding test plan (Person 2000) and are not within the scope of this SAP. This report provides the general methodology and procedures to be used in the preparation, retrieval, transport, analysis, and reporting of results from grab samples retrieved from tank 241-AP-104.

  8. Nuclear reactor

    International Nuclear Information System (INIS)

    Cover gas spaces for primary coolant vessel, such as a reactor container, a pump vessel and an intermediate heat exchanger vessel are in communication with each other by an inverted U-shaped pressure conduit. A transmitter and a receiver are disposed to the pressure conduit at appropriate positions. If vibration frequencies (pressure vibration) from low frequency to high frequency are generated continuously from the transmitter to the inside of the communication pipe, a resonance phenomenon (air-column resonance oscillation) is caused by the inherent frequency or the like of the communication pipe. The frequency of the air-column resonance oscillation is changed by the inner diameter and the clogged state of the pipelines. Accordingly, by detecting the change of the air-column oscillation characteristics by the receiver, the clogged state of the flow channels in the pipelines can be detected even during the reactor operation. With such procedures, steams of coolants flowing entrained by the cover gases can be prevented from condensation and coagulation at a low temperature portion of the pipelines, otherwise it would lead clogging in the pipelines. (I.N.)

  9. Study of Cost Effective Large Advanced Pressurized Water Reactors that Employ Passive Safety Features

    International Nuclear Information System (INIS)

    A report of DOE sponsored portions of AP1000 Design Certification effort. On December 16, 1999, The United States Nuclear Regulatory Commission issued Design Certification of the AP600 standard nuclear reactor design. This culminated an 8-year review of the AP600 design, safety analysis and probabilistic risk assessment. The AP600 is a 600 MWe reactor that utilizes passive safety features that, once actuated, depend only on natural forces such as gravity and natural circulation to perform all required safety functions. These passive safety systems result in increased plant safety and have also significantly simplified plant systems and equipment, resulting in simplified plant operation and maintenance. The AP600 meets NRC deterministic safety criteria and probabilistic risk criteria with large margins. A summary comparison of key passive safety system design features is provided in Table 1. These key features are discussed due to their importance in affecting the key thermal-hydraulic phenomenon exhibited by the passive safety systems in critical areas. The scope of some of the design changes to the AP600 is described. These changes are the ones that are important in evaluating the passive plant design features embodied in the certified AP600 standard plant design. These design changes are incorporated into the AP1000 standard plant design that Westinghouse is certifying under 10 CFR Part 52. In conclusion, this report describes the results of the representative design certification activities that were partially supported by the Nuclear Energy Research Initiative. These activities are unique to AP1000, but are representative of research activities that must be driven to conclusion to realize successful licensing of the next generation of nuclear power plants in the United States

  10. Study of Cost Effective Large Advanced Pressurized Water Reactors that Employ Passive Safety Features

    Energy Technology Data Exchange (ETDEWEB)

    Winters, J. W.; Corletti, M. M.; Hayashi, Y.

    2003-11-12

    A report of DOE sponsored portions of AP1000 Design Certification effort. On December 16, 1999, The United States Nuclear Regulatory Commission issued Design Certification of the AP600 standard nuclear reactor design. This culminated an 8-year review of the AP600 design, safety analysis and probabilistic risk assessment. The AP600 is a 600 MWe reactor that utilizes passive safety features that, once actuated, depend only on natural forces such as gravity and natural circulation to perform all required safety functions. These passive safety systems result in increased plant safety and have also significantly simplified plant systems and equipment, resulting in simplified plant operation and maintenance. The AP600 meets NRC deterministic safety criteria and probabilistic risk criteria with large margins. A summary comparison of key passive safety system design features is provided in Table 1. These key features are discussed due to their importance in affecting the key thermal-hydraulic phenomenon exhibited by the passive safety systems in critical areas. The scope of some of the design changes to the AP600 is described. These changes are the ones that are important in evaluating the passive plant design features embodied in the certified AP600 standard plant design. These design changes are incorporated into the AP1000 standard plant design that Westinghouse is certifying under 10 CFR Part 52. In conclusion, this report describes the results of the representative design certification activities that were partially supported by the Nuclear Energy Research Initiative. These activities are unique to AP1000, but are representative of research activities that must be driven to conclusion to realize successful licensing of the next generation of nuclear power plants in the United States.

  11. Reactor internals and hold down spring stiffness/reaction calculation

    International Nuclear Information System (INIS)

    Background: Hold down spring is a structural component that supports the reactor pressure vessel. It is located between the flange and barrel components, and has a function that transfers the force caused by reactor pressure vessel cap to barrel flange. Purpose: This paper attempts to have an analysis calculation and comparison of AP1OOO and LPP Hold down spring. Methods: This article inherited Qinshan nuclear power hold down spring analysis method, use analytical method and FEM method to solve the problem. Results: The stress and deflection of HDS are calculated. Since the friction coefficient may have a large effect, the results of different friction coefficients are also analyzed. Conclusions: This paper compared the Qinshan, AP1000 and LPP HDS design advantages and disadvantages and proposed two kinds of new design, expected to have a reference value for follow-up engineers. (authors)

  12. Fuel Summary Report: Shippingport Light Water Breeder Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Illum, D.B.; Olson, G.L.; McCardell, R.K.

    1999-01-01

    The Shippingport Light Water Breeder Reactor (LWBR) was a small water cooled, U-233/Th-232 cycle breeder reactor developed by the Pittsburgh Naval Reactors to improve utilization of the nation's nuclear fuel resources in light water reactors. The LWBR was operated at Shippingport Atomic Power Station (APS), which was a Department of Energy (DOE) (formerly Atomic Energy Commission)-owned reactor plant. Shippingport APS was the first large-scale, central-station nuclear power plant in the United States and the first plant of such size in the world operated solely to produce electric power. The Shippingport LWBR was operated successfully from 1977 to 1982 at the APS. During the five years of operation, the LWBR generated more than 29,000 effective full power hours (EFPH) of energy. After final shutdown, the 39 core modules of the LWBR were shipped to the Expended Core Facility (ECF) at Naval Reactors Facility at the Idaho National Engineering and Environmental Laboratory (INEEL). At ECF, 12 of the 39 modules were dismantled and about 1000 of more than 17,000 rods were removed from the modules of proof-of-breeding and fuel performance testing. Some of the removed rods were kept at ECF, some were sent to Argonne National Laboratory-West (ANL-W) in Idaho and some to ANL-East in Chicago for a variety of physical, chemical and radiological examinations. All rods and rod sections remaining after the experiments were shipped back to ECF, where modules and loose rods were repackaged in liners for dry storage. In a series of shipments, the liners were transported from ECF to Idaho Nuclear Technology Engineering Center (INTEC), formerly the Idaho Chemical Processing Plant (ICPP). The 47 liners containing the fully-rodded and partially-derodded core modules, the loose rods, and the rod scraps, are now stored in underground dry wells at CPP-749.

  13. Fuel Summary Report: Shippingport Light Water Breeder Reactor

    International Nuclear Information System (INIS)

    The Shippingport Light Water Breeder Reactor (LWBR) was a small water cooled, U-233/Th-232 cycle breeder reactor developed by the Pittsburgh Naval Reactors to improve utilization of the nation's nuclear fuel resources in light water reactors. The LWBR was operated at Shippingport Atomic Power Station (APS), which was a Department of Energy (DOE) (formerly Atomic Energy Commission)-owned reactor plant. Shippingport APS was the first large-scale, central-station nuclear power plant in the United States and the first plant of such size in the world operated solely to produce electric power. The Shippingport LWBR was operated successfully from 1977 to 1982 at the APS. During the five years of operation, the LWBR generated more than 29,000 effective full power hours (EFPH) of energy. After final shutdown, the 39 core modules of the LWBR were shipped to the Expended Core Facility (ECF) at Naval Reactors Facility at the Idaho National Engineering and Environmental Laboratory (INEEL). At ECF, 12 of the 39 modules were dismantled and about 1000 of more than 17,000 rods were removed from the modules of proof-of-breeding and fuel performance testing. Some of the removed rods were kept at ECF, some were sent to Argonne National Laboratory-West (ANL-W) in Idaho and some to ANL-East in Chicago for a variety of physical, chemical and radiological examinations. All rods and rod sections remaining after the experiments were shipped back to ECF, where modules and loose rods were repackaged in liners for dry storage. In a series of shipments, the liners were transported from ECF to Idaho Nuclear Technology Engineering Center (INTEC), formerly the Idaho Chemical Processing Plant (ICPP). The 47 liners containing the fully-rodded and partially-derodded core modules, the loose rods, and the rod scraps, are now stored in underground dry wells at CPP-749

  14. Functional analysis of the two Brassica AP3 genes involved in apetalous and stamen carpelloid phenotypes.

    Directory of Open Access Journals (Sweden)

    Yanfeng Zhang

    Full Text Available The Arabidopsis homeotic genes APETALA3 (AP3 and PISTILLATA (PI are B genes which encode MADS-box transcription factors and specify petal and stamen identities. In the current study, the stamen carpelloid (SC mutants, HGMS and AMS, of B. rapa and B. napus were investigated and two types of AP3 genes, B.AP3.a and B.AP3.b, were functional characterized. B.AP3.a and B.AP3.b share high similarity in amino acid sequences except for 8 residues difference located at the C-terminus. Loss of this 8 residues in B.AP3.b led to the change of PI-derived motifs. Meanwhile, B.AP3.a specified petal and stamen development, whereas B.AP3.b only specified stamen development. In B. rapa, the mutations of both genes generated the SC mutant HGMS. In B. napus that contained two B.AP3.a and two B.AP3.b, loss of the two B.AP3.a functions was the key reason for the apetalous mutation, however, the loss-of-function in all four AP3 was related to the SC mutant AMS. We inferred that the 8 residues or the PI-derived motif in AP3 gene probably relates to petal formation.

  15. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T. (Inventor); Sahimi, Muhammad (Inventor); Fayyaz-Najafi, Babak (Inventor); Harale, Aadesh (Inventor); Park, Byoung-Gi (Inventor); Liu, Paul K. T. (Inventor)

    2011-01-01

    A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

  16. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T.; Sahimi, Muhammad; Fayyaz-Najafi, Babak; Harale, Aadesh; Park, Byoung-Gi; Liu, Paul K. T.

    2011-03-01

    A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

  17. Relevant thermal hydraulic aspects of advanced reactors design: status report

    International Nuclear Information System (INIS)

    This status report provides an overview on the relevant thermalhydraulic aspects of advanced reactor designs (e.g. ABWR, AP600, SBWR, EPR, ABB 80+, PIUS, etc.). Since all of the advanced reactor concepts are at the design stage, the information and data available in the open literature are still very limited. Some characteristics of advanced reactor designs are provided together with selected phenomena identification and ranking tables. Specific needs for thermalhydraulic codes together with the list of relevant and important thermalhydraulic phenomena for advanced reactor designs are summarized with the purpose of providing some guidance in development of research plans for considering further code development and assessment needs and for the planning of experimental programs

  18. Functional Analysis of the Two Brassica AP3 Genes Involved in Apetalous and Stamen Carpelloid Phenotypes

    OpenAIRE

    Zhang, Yanfeng; Wang, Xuefang; Zhang, Wenxue; Yu, Fei; Tian, Jianhua; Li, Dianrong; Guo, Aiguang

    2011-01-01

    The Arabidopsis homeotic genes APETALA3 (AP3) and PISTILLATA (PI) are B genes which encode MADS-box transcription factors and specify petal and stamen identities. In the current study, the stamen carpelloid (SC) mutants, HGMS and AMS, of B. rapa and B. napus were investigated and two types of AP3 genes, B.AP3.a and B.AP3.b, were functional characterized. B.AP3.a and B.AP3.b share high similarity in amino acid sequences except for 8 residues difference located at the C-terminus. Loss of this 8...

  19. Reactor container

    International Nuclear Information System (INIS)

    Purpose: To prevent shocks exerted on a vent head due to pool-swell caused within a pressure suppression chamber (disposed in a torus configuration around the dry well) upon loss of coolant accident in BWR type reactors. Constitution: The following relationship is established between the volume V (m3) of a dry well and the ruptured opening area A (m2) at the boundary expected upon loss of coolant accident: V >= 30340 (m) x A Then, the volume of the dry well is made larger than the ruptured open area, that is, the steam flow rate of leaking coolants upon loss of coolant accident to decrease the pressure rise in the dry well at the initial state where loss of coolant accident is resulted. Accordingly, the pressure of non-compressive gases jetted out from the lower end of the downcomer to the pool water is decreased to suppress the pool-swell. (Ikeda, J.)

  20. Analysis of large scale tests for AP-600 passive containment cooling system

    International Nuclear Information System (INIS)

    One unique feature of the AP-600 is its passive containment cooling system (PCCS), which is designed to maintain containment pressure below the design limit for 72 hours without action by the reactor operator. During a design-basis accident, i.e., either a loss-of-coolant or a main steam-line break accident, steam escapes and comes in contact with the much cooler containment vessel wall. Heat is transferred to the inside surface of the steel containment wall by convection and condensation of steam and through the containment steel wall by conduction. Heat is then transferred from the outside of the containment surface by heating and evaporation of a thin liquid film that is formed by applying water at the top of the containment vessel dome. Air in the annual space is heated by both convection and injection of steam from the evaporating liquid film. The heated air and vapor rise as a result of natural circulation and exit the shield building through the outlets above the containment shell. All of the analytical models that are developed for and used in the COMMIX-ID code for predicting performance of the PCCS will be described. These models cover governing conservation equations for multicomponents single phase flow, transport equations for the κ-ε two-equation turbulence model, auxiliary equations, liquid-film tracking model for both inside (condensate) and outside (evaporating liquid film) surfaces of the containment vessel wall, thermal coupling between flow domains inside and outside the containment vessel, and heat and mass transfer models. Various key parameters of the COMMIX-ID results and corresponding AP-600 PCCS experimental data are compared and the agreement is good. Significant findings from this study are summarized

  1. Microbial community analysis of anaerobic reactors treating soft drink wastewater.

    Directory of Open Access Journals (Sweden)

    Takashi Narihiro

    Full Text Available The anaerobic packed-bed (AP and hybrid packed-bed (HP reactors containing methanogenic microbial consortia were applied to treat synthetic soft drink wastewater, which contains polyethylene glycol (PEG and fructose as the primary constituents. The AP and HP reactors achieved high COD removal efficiency (>95% after 80 and 33 days of the operation, respectively, and operated stably over 2 years. 16S rRNA gene pyrotag analyses on a total of 25 biofilm samples generated 98,057 reads, which were clustered into 2,882 operational taxonomic units (OTUs. Both AP and HP communities were predominated by Bacteroidetes, Chloroflexi, Firmicutes, and candidate phylum KSB3 that may degrade organic compound in wastewater treatment processes. Other OTUs related to uncharacterized Geobacter and Spirochaetes clades and candidate phylum GN04 were also detected at high abundance; however, their relationship to wastewater treatment has remained unclear. In particular, KSB3, GN04, Bacteroidetes, and Chloroflexi are consistently associated with the organic loading rate (OLR increase to 1.5 g COD/L-d. Interestingly, KSB3 and GN04 dramatically decrease in both reactors after further OLR increase to 2.0 g COD/L-d. These results indicate that OLR strongly influences microbial community composition. This suggests that specific uncultivated taxa may take central roles in COD removal from soft drink wastewater depending on OLR.

  2. To question of NPP power reactor choice for Kazakhstan

    International Nuclear Information System (INIS)

    Full text: The requirements to NPP power reactors that will be under construction in Kazakhstan are proved and given in the report. A comparative analysis of the most advanced projects of power reactors with light and heavy water under pressure of large, medium and low power is carried out. Different reactors have been considered as follows: 1. Reactors with high-power (700 MW(el) and up) such as EPR, French - German reactor; CANDU-9, Canadian heavy-water reactor; System 80+, developed by ABB Combustion Engineering company, USA; KNGR, Korean reactor of the next generation; APWR, Japanese advanced reactor; WWER-1000 (V-392) - development of Atomenergoproect /Gydropress, Russian Federation; EP 1000, European passive reactor. 2. Reactors with medium power (300 MW (el) - 700 MW (el): AP-600, passive PWR of the Westinghouse company; CANDU-6, Canadian heavy-water reactor; AC-600, Chinese passive PWR; WWER-640, Russian passive reactor; MS-600 Japanese reactor of Mitsubishi Company; KSNP-600, South Korean reactor. 3. Reactors with low power (a few MW(el)- 300 MW(el)): IRIS, reactor of IV generation, developed by the International Corporation of 13 organizations from 7 countries, SMART, South Korean integrated reactor; CAREM, Argentina integrated reactor; MRX, Japanese integrated reactor; 'UNITERM', Russian NPP with integrated reactor, development of NIKIET; AHEC-80, Russian NPP, developed by OKBM. A comparison of the projects of the above-mentioned power reactors was carried out with respect to 15 criteria of nuclear, radiating, ecological safety and economic competitiveness, developed especially for this case. Data on a condition and prospects of power production and power consumption, stations and networks in Kazakhstan necessary for the choice of projects of NPP reactors for Kazakhstan are given. According to the data a balance of power production and power consumption as a whole in the country was received at the level of 59 milliard kw/h. However, strong dis balance

  3. To question of NPP power reactor choice for Kazakhstan

    International Nuclear Information System (INIS)

    The requirements to NPP power reactors that will be under construction in Kazakhstan are proved and given in the report. A comparative analysis of the most advanced projects of power reactors with light and heavy water under pressure of large, medium and low power is carried out. Different reactors have been considered as follows: 1. Reactors with high-power (700 MW(el) and up) such as EPR, French - German reactor; CANDU-9, Canadian heavy-water reactor; System 80+, developed by ABB Combustion Engineering company, USA; KNGR, Korean reactor of the next generation; APWR, Japanese advanced reactor; WWER-1000 (V-392) - development of Atomenergoproect /Gydropress, Russian Federation; EP 1000, European passive reactor. 2. Reactors with medium power (300 MW (el) - 700 MW (el): AP-600, passive PWR of the Westinghouse company; CANDU-6, Canadian heavy-water reactor; AC-600, Chinese passive PWR; WWER-640, Russian passive reactor; MS-600 Japanese reactor of Mitsubishi Company; KSNP-600, South Korean reactor. 3. Reactors with low power (a few MW(el)- 300 MW(el)): IRIS, reactor of IV generation, developed by the International Corporation of 13 organizations from 7 countries, SMART, South Korean integrated reactor; CAREM, Argentina integrated reactor; MRX, Japanese integrated reactor; 'UNITERM', Russian NPP with integrated reactor, development of NIKIET; AHEC-80, Russian NPP, developed by OKBM. A comparison of the projects of the above-mentioned power reactors was carried out with respect to 15 criteria of nuclear, radiating, ecological safety and economic competitiveness, developed especially for this case. Data on a condition and prospects of power production and power consumption, stations and networks in Kazakhstan necessary for the choice of projects of NPP reactors for Kazakhstan are given. According to the data a balance of power production and power consumption as a whole in the country was received at the level of 59 milliard kw/h. However, strong dis balance in the

  4. Numerical study on seismic response of the reactor coolant pump in Advanced Passive Pressurized Water Reactor

    International Nuclear Information System (INIS)

    Highlights: • An artificial accelerogram of the specified SSE is generated. • A dynamic FE model of the RCP in AP1000 (with gyroscopic and FSI effects) is developed. • The displacement, force, moment and stress in the RCP during the earthquake are summarized. - Abstract: The reactor coolant pump in the Advanced Passive Pressurized Water Reactor is a kind of nuclear canned-motor pump. The pump is classified as Seismic Category I, which must function normally during the Safe Shutdown Earthquake. When the nuclear power plant is located in seismically active region, the seismic response of the reactor coolant pump may become very important for the safety assessment of the whole nuclear power plant. In this article, an artificial accelerogram is generated. The response spectrum of the artificial accelerogram fits well with the design acceleration spectrum of the Safe Shutdown Earthquake. By applying the finite element modeling method, the dynamic finite element models of the rotor and stator in the reactor coolant pump are created separately. The rotor and stator are coupled by the journal bearings and the annular flow between the rotor and stator. Then the whole dynamic model of the reactor coolant pump is developed. Time domain analysis which uses the improved state-space Newmark method of a direct time integration scheme is carried out to investigate the response of the reactor coolant pump under the horizontal seismic load. The results show that the reactor coolant pump responds differently in the direction of the seismic load and in the perpendicular direction. During the Safe Shutdown Earthquake, the displacement response, the shear force, the moment and the journal bearing reaction forces in the reactor coolant pump are analyzed

  5. Numerical study on seismic response of the reactor coolant pump in Advanced Passive Pressurized Water Reactor

    Energy Technology Data Exchange (ETDEWEB)

    De, Cheng, E-mail: 0100209064@sjtu.edu.cn; Zhen-Qiang, Yao, E-mail: zqyaosjtu@gmail.com; Ya-bo, Xue; Hong, Shen

    2014-10-15

    Highlights: • An artificial accelerogram of the specified SSE is generated. • A dynamic FE model of the RCP in AP1000 (with gyroscopic and FSI effects) is developed. • The displacement, force, moment and stress in the RCP during the earthquake are summarized. - Abstract: The reactor coolant pump in the Advanced Passive Pressurized Water Reactor is a kind of nuclear canned-motor pump. The pump is classified as Seismic Category I, which must function normally during the Safe Shutdown Earthquake. When the nuclear power plant is located in seismically active region, the seismic response of the reactor coolant pump may become very important for the safety assessment of the whole nuclear power plant. In this article, an artificial accelerogram is generated. The response spectrum of the artificial accelerogram fits well with the design acceleration spectrum of the Safe Shutdown Earthquake. By applying the finite element modeling method, the dynamic finite element models of the rotor and stator in the reactor coolant pump are created separately. The rotor and stator are coupled by the journal bearings and the annular flow between the rotor and stator. Then the whole dynamic model of the reactor coolant pump is developed. Time domain analysis which uses the improved state-space Newmark method of a direct time integration scheme is carried out to investigate the response of the reactor coolant pump under the horizontal seismic load. The results show that the reactor coolant pump responds differently in the direction of the seismic load and in the perpendicular direction. During the Safe Shutdown Earthquake, the displacement response, the shear force, the moment and the journal bearing reaction forces in the reactor coolant pump are analyzed.

  6. No oxygen isotope exchange between water and APS-sulfate at surface temperature: Evidence from quantum chemical modeling and triple-oxygen isotope experiments

    Science.gov (United States)

    Kohl, Issaku E.; Asatryan, Rubik; Bao, Huiming

    2012-10-01

    In both laboratory experiments and natural environments where microbial dissimilatory sulfate reduction (MDSR) occurs in a closed system, the δ34S ((34S/32S)sample/(34S/32S)standard - 1) for dissolved SO42- has been found to follow a typical Rayleigh-Distillation path. In contrast, the corresponding δ18O ((18O/16O)sample/(18O/16O)standard) - 1) is seen to plateau with an apparent enrichment of between 23‰ and 29‰ relative to that of ambient water under surface conditions. This apparent steady-state in the observed difference between δ18O and δ18OO can be attributed to any of these three steps: (1) the formation of adenosine-5'-phosphosulfate (APS) from ATP and SO42-, (2) oxygen exchange between sulfite (or other downstream sulfoxy-anions) and water later in the MDSR reaction chain and its back reaction to APS and sulfate, and (3) the re-oxidation of produced H2S or precursor sulfoxy-anions to sulfate in environments containing Fe(III) or O2. This study examines the first step as a potential pathway for water oxygen incorporation into sulfate. We examined the structures and process of APS formation using B3LYP/6-31G(d,p) hybrid density functional theory, implemented in the Gaussian-03 program suite, to predict the potential for oxygen exchange. We conducted a set of in vitro, enzyme-catalyzed, APS formation experiments (with no further reduction to sulfite) to determine the degree of oxygen isotope exchange between the APS-sulfate and water. Triple-oxygen-isotope labeled water was used in the reactor solutions to monitor oxygen isotope exchange between water and APS sulfate. The formation and hydrolysis of APS were identified as potential steps for oxygen exchange with water to occur. Quantum chemical modeling indicates that the combination of sulfate with ATP has effects on bond strength and symmetry of the sulfate. However, these small effects impart little influence on the integrity of the SO42- tetrahedron due to the high activation energy required for

  7. SPES-2, the full-height, full-pressure test facility simulating the AP600 plant comparison among 2' small break tests located on different lines

    International Nuclear Information System (INIS)

    SPES-2 is a full height, full pressure experimental test facility reproducing the Westinghouse AP600 reactor with a scaling factor of 1/395. The experimental plant, designed and operated by SIET in Piacenza, consists of a full simulation of the AP600 primary core cooling system including all the passive and active safety systems. In 1992, Westinghouse, in cooperation with ENEL, ENEA, SIET and ANSALDO developed an experimental program to test the integrated behaviour of the AP600 passive safety systems. The SPES-2 test matrix, concluded in November'94, has examined the AP600 passive safety system response for a range of small break LOCAs at different locations on the primary system and on the passive system lines; single steam generator tube ruptures with both passive and active non-safety systems, and a main steam line break transient to demonstrate the capability of passive safety systems for rapid cooldown. Each of the tests has provided detailed experimental results for verification of the capability of the analysis methods to predict the integrated passive safety system behaviour. The author will describe the results obtained during experimental test facility having the same break size (2 inches) but located in different plant positions (cold leg, Direct Vessel Injection line, cold leg-CMT balance line) in order to determine the effect of break location on the plant behaviour

  8. Tank 241-AP-107 tank characterization plan. Revision 1

    International Nuclear Information System (INIS)

    Defense Nuclear Facilities Safety Board has directed the DOE to concentrate ear-term sampling and analysis activities on identification and resolution of issues (Conway 1993). The Data Quality Objective (DQO) process was chosen as a tool to be used in the resolution of safety issues. As a result, a revision in the Federal Facilities Agreement and Consent Order (Tri-Party Agreement) milestone M-44-00 has been made, which states that ''A Tank Characterization Plan (TCP) will be developed for each double-shell tank (DST) and single-shell tank (SST) using the DQO process; Development of TCPs by the DQO process is intended to allow users (e.g., Hanford Facility user groups, regulators) to ensure their needs will be met and that resources are devoted to gaining only necessary information.'' This document satisfies that requirement for the tank 241-AP-107 (AP-107)

  9. Status of APS 1-Mwe Parabolic Trough Project

    Energy Technology Data Exchange (ETDEWEB)

    Canada, S.; Brosseau, D.; Kolb, G.; Moore, L.; Cable, R.; Price, H.

    2005-11-01

    Arizona Public Service (APS) is currently installing new power facilities to generate a portion of its electricity from solar resources that will satisfy its obligation under the Arizona Environmental Portfolio Standard (EPS). During FY04, APS began construction on a 1-MWe parabolic trough concentrating solar power plant. This plant represents the first parabolic trough plant to begin construction since 1991. Site preparation and construction activities continued throughout much of FY05, and startup activities are planned for Fall 2005 (with completion early in FY06). The plant will be the first commercial deployment of the Solargenix parabolic trough collector technology developed under contract to the National Renewable Energy Laboratory. The plant will use an organic Rankine cycle (ORC) power plant, provided by Ormat. The ORC power plant is much simpler than the conventional steam Rankine cycle plant and allows unattended operation of the facility.

  10. Densification and microstructure development during HIPing of AP1

    International Nuclear Information System (INIS)

    The densification and the microstructural development during hot isostatic pressing of AP1 superalloy powder were compared with the predictions made from calculated HIP diagrams. Power law creep was found to dominate the densification of the Ni-base superalloy during HIPing. The densification was in accordance with calculated HIP maps at low pressures and annealing times, but at elevated pressures and prolonged HIPing times much faster than calculated. During HIPing some percent of the particles undergo minor deformation. It was found in AP1 that these particles showed coarse grains, whereas the more heavily deformed particles displayed a fine microstructure. The different degrees of deformation may arise from size differences of the particles. (orig.)

  11. Comparative advantages of AP1000 passive safety system

    International Nuclear Information System (INIS)

    With the increasing need of nuclear power, almost all countries who want to build new nuclear power plant take the generation Ⅲ technology as their first choice. The main reason is that the safety of generation Ⅲ technology has been improved greatly than generation Ⅱ and Ⅱ + technology. The passive safety technology is introduced by AP1000 and it is one of the best in generation Ⅲ technologies. The representative passive containment cooling system of AP1000 and containment spray system of generation Ⅱ nuclear power plant were compared in the paper and analyzed using probabilistic safety assessment method. The reasons of passive safety system possessing comparative advantages were obtained by the concrete calculation. (authors)

  12. Top-mounted in-core instrumentation insertion test for westinghouse AP1000

    International Nuclear Information System (INIS)

    The Westinghouse AP1000 will employ top-mounted, fixed in-core detectors designated in-core Instrument Thimble Assemblies (IITA). For the first time, a Westinghouse in-core instrumentation system will require reactor vessel closure head penetrations, and guide tubes throughout the integrated head package and reactor upper internals. Therefore, as part of the IITA design validation, a test using a full scale mock up of the detector and its guide path was conducted in order to measure the forces exerted on the IITA upon insertion into and withdrawal from the limiting guide path. The purpose of this test was to determine if the IITA can be manually inserted into the guide path over its design lifetime. In order to simulate wear and possible strain-hardening over the design life of the IITA, the insertion and withdrawal process was repeated 26 times. Strain-hardening of the detectors could cause the insertion and withdrawal forces to gradually increase with each insertion/withdrawal evolution. However, results showed that insertion forces actually decreased over time. The testing revealed guide path locations where significant increases in the required insertion force occurred. The testing also showed how the forces changed as the number of insertion/withdrawal cycles increased. The information from an initial test was used to benchmark an ANSYS model of the insertion test for use in evaluating design changes. The measured insertion and withdrawal forces collected from the guide path mock up, in coincidence with the observed ancillary changes in the physical characteristics of the detector assembly, and information from the ANSYS model have provided the designers with the information needed to greatly improve the AP1000 IITA Guide Path insertion/withdrawal characteristics. Testing of an Optimized ZIRLOTM IITA with incorporated changes to the insertion path has shown a dramatic decrease in the required insertion/withdrawal force and associated stresses. The results of

  13. Electron-cloud measurements and simulations for the APS

    International Nuclear Information System (INIS)

    We compare experimental results with simulations of the electron cloud effect induced by a positron beam at the APS synchrotron light source at ANL, where the electron cloud effect has been observed and measured with dedicated probes. We find good agreement between simulations and measurements for reasonable values of certain secondary electron yield (SEY) parameters, most of which were extracted from recent bench measurements at SLAC

  14. QCD on the highly parallel computer AP1000

    International Nuclear Information System (INIS)

    We have been running quenched QCD simulations on 324 and 323 x 48 lattices using a 512 processor AP1000, which is a highly parallel computer with up to 1024 processing elements. We have developed programs for update, blocking and hadron propagator calculations. The pseudo heatbath and the overrelaxation algorithms were used for the update with performance of 2.6 and 2.0 μsec/link, respectively. (orig.)

  15. Thermal analysis of the beam missteering in APS storage ring

    International Nuclear Information System (INIS)

    Several bending magnet beam missteering cases have been investigated for the 7-GeV storage ring of the Advanced Photon Source (APS). One of the critical missteering events is presented in this paper. Finite element analyses are performed to solve for both temperature and stress fields. Thermally induced deflections are determined by using beam bending theory. A safe current limit is established for the storage ring chambers

  16. Electron-cloud measurements and simulations for the APS

    OpenAIRE

    Furman, M.A.; Pivi, M.; Harkay, K.C.; Rosenberg, R. A.

    2001-01-01

    We compare experimental results with simulations of the electron cloud effect induced by a positron beam at the APS synchrotron light source at ANL, where the electron cloud effect has been observed and measured with dedicated probes. We find good agreement between simulations and measurements for reasonable values of certain secondary electron yield (SEY) parameters, most of which were extracted from recent bench measurements at SLAC.

  17. The interaction between the adaptor protein APS and Enigma is involved in actin organisation

    DEFF Research Database (Denmark)

    Barres, Romain; Gonzalez, Teresa; Le Marchand-Brustel, Yannick; Tanti, Jean-François

    2005-01-01

    APS (adaptor protein with PH and SH2 domains) is an adaptor protein phosphorylated by several tyrosine kinase receptors including the insulin receptor. To identify novel binding partners of APS, we performed yeast two-hybrid screening. We identified Enigma, a PDZ and LIM domain-containing protein...... that was previously shown to be associated with the actin cytoskeleton. In HEK 293 cells, Enigma interacted specifically with APS, but not with the APS-related protein SH2-B. This interaction required the NPTY motif of APS and the LIM domains of Enigma. In NIH-3T3 cells that express the insulin...... receptor, Enigma and APS were partially co-localised with F-actin in small ruffling structures. Insulin increased the complex formation between APS and Enigma and their co-localisation in large F-actin containing ruffles. While in NIH-3T3 and HeLa cells the co-expression of both Enigma and APS did not...

  18. Work plan, AP-102 mixer pump removal and pump replacement

    International Nuclear Information System (INIS)

    The objective of this work plan is to plan the steps and estimate the costs required to remove the failed AP-102 mixer pump, and to plan and estimate the cost of the necessary design and specification work required to order a new, but modified, mixer pump including the pump and pump pit energy absorbing design. The main hardware required for the removal of the mixer is as follows: a flexible receiver and blast shield; a metal container for the pulled mixer pump; and a trailer and strongback to haul and manipulate the container. Additionally: a gamma scanning device will be needed to detect the radioactivity emanating from the mixer as it is pulled from the tank; a water spray system will be required to remove tank waste from the surface of the mixer as it is pulled from the AP-102 tank; and a lifting yoke to lift the mixer from the pump pit (the SY-101 Mixer Lifting Yoke will be used). A ''green house'' will have to be erected over the AP-102 pump pit and an experienced Hoisting and Rigging crew must be assembled and trained in mixer pump removal methods before the actual removal is undertaken

  19. Alignment and commissioning of the APS beamline front ends

    International Nuclear Information System (INIS)

    Fifteen out of forty initial beamline front ends have been installed in the storage-ring tunnel at the 7-GeV Advanced Photon Source (APS). For the front-end installation, a four-step alignment process was designed and consists of (1) prealigning the front-end components with support tables in the preassembly area, (2) installing the components with tables in the storage-ring tunnel and aligning relative to the APS global telescope survey network, (3) confirming the alignment using a tooling laser alignment system, and (4) performing adjustments with the synchrotron-radiation beam during commissioning. The laser alignment system and the prealignment database have been of great importance for the expedient maintenance of front-end components. These tools are very important to a large synchrotron radiation facility, such as the APS, since they make a quick alignment setup possible and minimize alignment time inside the tunnel. This paper will present the four-step alignment process, the laser alignment system, and discuss the alignment confirmation results. copyright 1996 American Institute of Physics

  20. Finite element modeling of AP1000 nuclear island

    International Nuclear Information System (INIS)

    The AP1000 is a standard design developed by Westinghouse and its partners for an advanced nuclear power plant utilizing passive safety features. It is based on the certified design of the AP600 and has been uprated to 1000 MWe. The plant has five principal building structures; the nuclear island, the turbine building; the annex building; the diesel generator building and the radwaste building. The nuclear island consists of the containment building (the steel containment vessel and the containment internal structures), the shield building, and the auxiliary building. These structures are founded on a common basemat and are collectively known as the nuclear island. This paper describes use of the general purpose finite element program ANSYS [2] in structural analyses and qualification of the AP1000 nuclear island buildings. It describes the modeling of the shield building and the auxiliary building and the series of analyses and the flow of information from the global analyses to the detailed analyses and building qualification. (author)

  1. Standardized safety management of AP1000 nuclear power plant

    International Nuclear Information System (INIS)

    In 2002, China published and implemented the Law of the People's Republic of China on Work Safety and promulgated a series of guidelines and policies, which strengthened the safety management supervision. Standardization of safety, as another important step on safety supervision, comes after safety assesment and safety production licensing system, is also a permanent solution. Standardization of safety is a strategic, long term and fundamental work, which is also the basic access to achieving scientific safety management and increasing the inherent safety of an enterprise. Haiyang AP1000 nuclear power plant, adopting the modularized, 'open-top' and parallel construction means, overturned the traditional construction theory of installation work comes after the civil work and greatly shorten the construction period. At the same time, the notable increase of oversize module transportation and lifting and parallel construction raises higher demands for safety management. This article combines the characteristics and difficulties of safety management for Haiyang AP1000 nuclear power plant, puts forward ideas and methods for standardized safety management, and could also serve as reference to the safety management for other AP1000 projects. (authors)

  2. Long-term stability of the APS storage ring

    International Nuclear Information System (INIS)

    The Advanced Photon Source (APS), a third-generation synchrotrons light source, was commissioned in 1995 at Argonne ''National Laboratory and has been fully-operational for beamline users since 1997. The APS storage ring can accommodate up to 68 user beamlines; about 70% of the available beamlines are currently in use by various collaborative access teams (CATS). The 7-GeV synchrotrons light source produces light in the soft to hard x-ray range that is used for research in such areas as x-ray instrumentation; material, chemical and atomic sciences; biology; and geo/soil/ environmental sciences. For the successful operation of an x-ray light source such as the Advanced Photon Source, the long-term stability of the concrete floor supporting the beam components and user beamlines is crucial. Settlements impact the orbit and location of the x-ray source points as well as the position of the x-ray beamlines. This paper compares the results of two successive resurveys of the APS accelerator components performed in 1995 and 1998

  3. Maternal AP determinants in the Drosophila oocyte and embryo.

    Science.gov (United States)

    Ma, Jun; He, Feng; Xie, Gengqiang; Deng, Wu-Min

    2016-09-01

    An animal embryo cannot initiate its journey of forming a new life on its own. It must rely on maternally provided resources and inputs to kick-start its developmental process. In Drosophila, the initial polarities of the embryo along both the anterior-posterior (AP) and dorsal-ventral (DV) axes are also specified by maternal determinants. Over the past several decades, genetic and molecular studies have identified and characterized such determinants, as well as the zygotic genetic regulatory networks that control patterning in the early embryo. Extensive studies of oogenesis have also led to a detailed knowledge of the cellular and molecular interactions that control the formation of a mature egg. Despite these efforts, oogenesis and embryogenesis have been studied largely as separate problems, except for qualitative aspects with regard to maternal regulation of the asymmetric localization of maternal determinants. Can oogenesis and embryogenesis be viewed from a unified perspective at a quantitative level, and can that improve our understanding of how robust embryonic patterning is achieved? Here, we discuss the basic knowledge of the regulatory mechanisms controlling oogenesis and embryonic patterning along the AP axis. We explore properties of the maternal Bicoid gradient in relation to embryo size in search for a unified framework for robust AP patterning. WIREs Dev Biol 2016, 5:562-581. doi: 10.1002/wdev.235 For further resources related to this article, please visit the WIREs website. PMID:27253156

  4. Survey of research reactors

    International Nuclear Information System (INIS)

    A survey of reasearch reactors based on the IAEA Nuclear Research Reactor Data Base (RRDB) was done. This database includes information on 273 operating research reactors ranging in power from zero to several hundred MW. From these 273 operating research reactors 205 reactors have a power level below 5 MW, the remaining 68 reactors range from 5 MW up to several 100 MW thermal power. The major reactor types with common design are: Siemens Unterrichtsreaktors, 1.2 Argonaut reactors, Slowpoke reactors, the miniature neutron source reactors, TRIGA reactors, material testing reactors and high flux reactors. Technical data such as: power, fuel material, fuel type, enrichment, maximum neutron flux density and experimental facilities for each reactor type as well as a description of their utilization in physics and chemistry, medicine and biology, academic research and teaching, training purposes (students and physicists, operating personnel), industrial application (neutron radiography, silicon neutron transmutation doping facilities) are provided. The geographically distribution of these reactors is also shown. As conclusions the author discussed the advantages (low capital cost, low operating cost, low burn up, simple to operate, safe, less restrictive containment and sitting requirements, versatility) and disadvantages (lower sensitivity for NAA, limited radioisotope production, limited use of neutron beams, limited access to the core, licensing) of low power research reactors. 24 figs., refs. 15, Tab. 1 (nevyjel)

  5. Department of reactor technology

    International Nuclear Information System (INIS)

    The activities of the Department of Reactor Technology at Risoe during 1979 are described. The work is presented in five chapters: Reactor Engineering, Reactor Physics and Dynamics, Heat Transfer and Hydraulics, The DR 1 Reactor, and Non-Nuclear Activities. A list of the staff and of publications is included. (author)

  6. RB reactor noise analysis

    International Nuclear Information System (INIS)

    Statistical fluctuations of reactivity represent reactor noise. Analysis of reactor noise enables determining a series of reactor kinetic parameters. Fluctuations of power was measured by ionization chamber placed next to the tank of the RB reactor. The signal was digitized by an analog-digital converter. After calculation of the mean power, 3000 data obtained by sampling were analysed

  7. PolyADP-ribose polymerase is a coactivator for AP-2-mediated transcriptional activation.

    OpenAIRE

    Kannan, P; Yu, Y; Wankhade, S; Tainsky, M A

    1999-01-01

    Overexpression of transcription factor AP-2 has been implicated in the tumorigenicity of the human teratocarcinoma cell lines PA-1 that contain an activated ras oncogene. Here we show evidence that overexpression of AP-2 sequesters transcriptional coactivators which results in self-inhibition. We identified AP-2-interacting proteins and determined whether these proteins were coactivators for AP-2-mediated transcription. One such interacting protein is polyADP-ribose polymerase (PARP). PARP su...

  8. A novel AP4M1 mutation in autosomal recessive cerebral palsy syndrome and clinical expansion of AP-4 deficiency

    OpenAIRE

    Jameel, Muhammad; Klar, Joakim; Tariq, Muhammad; Moawia, Abubakar; Altaf Malik, Naveed; Seema Waseem, Syeda; Abdullah, Uzma; Naeem Khan, Tahir; Raininko, Raili; Baig, Shahid Mahmood; Dahl, Niklas

    2014-01-01

    BACKGROUND: Cerebral palsy (CP) is a heterogeneous neurodevelopmental disorder associated with intellectual disability in one-third of cases. Recent findings support Mendelian inheritance in subgroups of patients with the disease. The purpose of this study was to identify a novel genetic cause of paraplegic CP with intellectual disability in a consanguineous Pakistani family. METHODS: We performed whole-exome sequencing (WES) in two brothers with CP and intellectual disability. Analysis of AP...

  9. Role of the tryptophan residue in the vicinity of the catalytic center of exonuclease III family AP endonucleases: AP site recognition mechanism

    OpenAIRE

    Kaneda, Kohichi; Sekiguchi, Junichi; Shida, Toshio

    2006-01-01

    The mechanisms by which AP endonucleases recognize AP sites have not yet been determined. Based on our previous study with Escherichia coli exonuclease III (ExoIII), the ExoIII family AP endonucleases probably recognize the DNA-pocket formed at an AP site. The indole ring of a conserved tryptophan residue in the vicinity of the catalytic site presumably intercalates into this pocket. To test this hypothesis, we constructed a series of mutants of ExoIII and human APE1. Trp-212 of ExoIII and Tr...

  10. The AP-1 transcription factor homolog Pf-AP-1 activates transcription of multiple biomineral proteins and potentially participates in Pinctada fucata biomineralization

    OpenAIRE

    Xiangnan Zheng; Minzhang Cheng; Liang Xiang; Jian Liang; Liping Xie; Rongqing Zhang

    2015-01-01

    Activator protein-1 (AP-1) is an important bZIP transcription factor that regulates a series of physiological processes by specifically activating transcription of several genes, and one of its well-chartered functions in mammals is participating in bone mineralization. We isolated and cloned the complete cDNA of a Jun/AP-1 homolog from Pinctada fucata and called it Pf-AP-1. Pf-AP-1 had a highly conserved bZIP region and phosphorylation sites compared with those from mammals. A tissue distrib...

  11. NRC confirmatory AP600 safety system phase I testing in the ROSA/AP600 test facility

    Energy Technology Data Exchange (ETDEWEB)

    Rhee, G.S.; Kukita, Yutaka; Schultz, R.R.

    1996-03-01

    The NRC confirmatory phase I testing for the AP600 safety systems has been completed in the modified ROSA (Rig of Safety Assessment) test facility located at the Japan Atomic Energy Research Institute (JAERI) campus in Tokai, Japan. The test matrix included a variety of accident scenarios covering both design and beyond-design basis accidents. The test results indicate the AP600 safety systems as reflected in ROSA appear to perform as designed and there is no danger of core heatup for the accident scenarios investigated. In addition, no detrimental system interactions nor adverse effects of non-safety systems on the safety system functions were identified. However, three phenomena of interest have been identified for further examination to determine whether they are relevant to the AP600 plant. Those three phenomena are: (1) a potential for water hammer caused by rapid condensation which may occur following the actuation of the automatic depressurization system (ADS), (2) a large thermal gradient in the cold leg pipe where cooled water returns from the passive residual heat removal system and forms a thermally stratified layer, and (3) system-wide oscillations initiating following the ADS stage 4 actuation and persisting until the liquid in the pressurizer drains and steam generation in the core becomes insignificant.

  12. Research Nuclear Reactors

    International Nuclear Information System (INIS)

    Published in English and in French, this large report first proposes an overview of the use and history of research nuclear reactors. It discusses their definition, and presents the various types of research reactors which can be either related to nuclear power (critical mock-ups, material test reactors, safety test reactors, training reactors, prototypes), or to research (basic research, industry, health), or to specific particle physics phenomena (neutron diffraction, isotope production, neutron activation, neutron radiography, semiconductor doping). It reports the history of the French research reactors by distinguishing the first atomic pile (ZOE), and the activities and achievements during the fifties, the sixties and the seventies. It also addresses the development of instrumentation for research reactors (neutron, thermal, mechanical and fission gas release measurements). The other parts of the report concern the validation of neutronics calculations for different reactors (the EOLE water critical mock-up, the MASURCA air critical mock-up dedicated to fast neutron reactor study, the MINERVE water critical mock-up, the CALIBAN pulsed research reactor), the testing of materials under irradiation (OSIRIS reactor, laboratories associated with research reactors, the Jules Horowitz reactor and its experimental programs and related devices, irradiation of materials with ion beams), the investigation of accident situations (on the CABRI, Phebus, Silene and Jules Horowitz reactors). The last part proposes a worldwide overview of research reactors

  13. Reactor Physics Training

    International Nuclear Information System (INIS)

    University courses in nuclear reactor physics at the universities consist of a theoretical description of the physics and technology of nuclear reactors. In order to demonstrate the basic concepts in reactor physics, training exercises in nuclear reactor installations are also desirable. Since the number of reactor facilities is however strongly decreasing in Europe, it becomes difficult to offer to students a means for demonstrating the basic concepts in reactor physics by performing training exercises in nuclear installations. Universities do not generally possess the capabilities for performing training exercises. Therefore, SCK-CEN offers universities the possibility to perform (on a commercial basis) training exercises at its infrastructure consisting of two research reactors (BR1 and VENUS). Besides the organisation of training exercises in the framework of university courses, SCK-CEN also organizes theoretical courses in reactor physics for the education and training of nuclear reactor operators. It is indeed a very important subject to guarantee the safe operation of present and future nuclear reactors. In this framework, an understanding of the fundamental principles of nuclear reactor physics is also necessary for reactor operators. Therefore, the organisation of a basic Nuclear reactor physics course at the level of reactor operators in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The objectives this activity are: (1) to provide training and education activities in reactor physics for university students and (2) to organise courses in nuclear reactor physics for reactor operators

  14. Introduction of Nuclear Reactor Engineering

    International Nuclear Information System (INIS)

    This book introduces development, status, supply and demand and resource of nuclear reactor. It deals with basic knowledge of nuclear reactor, which are reactor system, heat recovery in reactor core, structural feature in reactor, materials of structure in reactor, shielding of gamma ray, shielding of reactor, safety and environmental problem of nuclear power plant, nuclear fuel and economical efficiency of nuclear energy.

  15. AP4 directly downregulates p16 and p21 to suppress senescence and mediate transformation

    OpenAIRE

    Jackstadt, R; Jung, P.; Hermeking, H

    2013-01-01

    Here we analyzed the function of the c-MYC-inducible basic helix–loop–helix leucine-zipper transcription factor AP4 in AP4-deficient mouse embryo fibroblasts (MEFs). Loss of AP4 resulted in premature senescence and resistance towards immortalization. Senescence was accompanied by induction of the cyclin-dependent kinase inhibitor-encoding genes p16, a known tumor suppressor, and p21, a previously described target for repression by AP4. Notably, AP4 directly repressed p16 expression via conser...

  16. Packaging design criteria, transfer and disposal of 102-AP mixer pump

    International Nuclear Information System (INIS)

    A mixer pump installed in storage tank 241-AP-102 (102-AP) has failed. This pump is referred to as the 102-AP mixer pump (APMP). The APMP will be removed from 102-AP 1 and a new pump will be installed. The main purpose of the Packaging Design Criteria (PDC) is to establish criteria necessary to design and fabricate a shipping container for the transfer and storage of the APMP from 102-AP. The PDC will be used as a guide to develop a Safety Evaluation for Packaging (SEP)

  17. Epidemiological studies in Russia about the consequences of the Chernobyl APS accident

    Energy Technology Data Exchange (ETDEWEB)

    Ryabzev, I.A. [Institute of Problem of Ecology and Evolution, Russian Academy of Sciences, Moscow (Russian Federation)

    1998-03-01

    The final purpose of all efforts to study and mitigate the consequences of the accident at the 4th reactor of the Chernobyl atomic power station (ChAPS) is protection of health of the people who were more or less exposed to radiation action. This situation has not analogs in terms of scale and character. Certain experience was accumulated earlier through the studies of biological and medical effects of atomic bombing in Hiroshima and Nagasaki, other radiation catastrophes, diagnostic and therapeutic application of radiation, and the control of health state of professionals in atomic industries. However, these experiences can be used just partially in the assessment and the forecast of possible negative after-effects of the Chernobyl accident for the present and future generations. The long-term irradiation of a lage number of population at low doses is to be considered the principal peculiarity of the Chernobyl accident. The medical activities are complicated significantly by the absence of verifiable individual dosimetric information, natural or forced migration of the population, insufficient development of radiation epidemiology, complicated social-economic situation in the country, and other factors which are inevitable at large-scaled catastrophes. Besides, many fundamental questions related to biological effects of action of low doses of ionizing radiation are still being studied. (J.P.N.)

  18. Piping Stress analysis for primary system of nuclear power plant AP-600

    International Nuclear Information System (INIS)

    Piping stress analysis for AP-600 primary system has been done using software CAEPIPE and PS-CAEPIPE. The loading applied to the system are static and seismic category I and II piping in reactor building have been analysed, those are PXS-900, CVS-110, PCS-030, CAS-700 and CCS-050. These system contain pipes with the normal diameter of 1,2, 4and 8. The design pressures are in the range of 150oF to 300oF. The acceleration taken as input in PS-CAEPIPE is based on seismic response spectra of floor the piping is located. In CAEPIPE, the acceleration taken from the peak of response spectra multiplied by 1.7 all of the acceleration in this case are no more than 0.36g. The result shows that after locating some supports, all system are acceptable without snubbers. The maximum stress are 11210 psi for deadweight load and 35593 psi for total load (the allowable values are 15000 psi and 45000 psi). The maximum displacement are 0.123 in for deadweight load, 1.474 in for hot load seismic load (the allowable values are 0.125 in for deadweight and 2.5 in for total load). The difference results of the both software is mainly in seismic calculation where mare parameters can be evaluated by PS-CAEPIPE including to evaluate valves acceleration in seismic condition

  19. Safeguarding research reactors

    International Nuclear Information System (INIS)

    The report is organized in four sections, including the introduction. The second section contains a discussion of the characteristics and attributes of research reactors important to safeguards. In this section, research reactors are described according to their power level, if greater than 25 thermal megawatts, or according to each fuel type. This descriptive discussion includes both reactor and reactor fuel information of a generic nature, according to the following categories. 1. Research reactors with more than 25 megawatts thermal power, 2. Plate fuelled reactors, 3. Assembly fuelled reactors. 4. Research reactors fuelled with individual rods. 5. Disk fuelled reactors, and 6. Research reactors fuelled with aqueous homogeneous fuel. The third section consists of a brief discussion of general IAEA safeguards as they apply to research reactors. This section is based on IAEA safeguards implementation documents and technical reports that are used to establish Agency-State agreements and facility attachments. The fourth and last section describes inspection activities at research reactors necessary to meet Agency objectives. The scope of the activities extends to both pre and post inspection as well as the on-site inspection and includes the examination of records and reports relative to reactor operation and to receipts, shipments and certain internal transfers, periodic verification of fresh fuel, spent fuel and core fuel, activities related to containment and surveillance, and other selected activities, depending on the reactor

  20. Research nuclear reactors

    International Nuclear Information System (INIS)

    Since the divergence of the first nuclear reactor in 1942, about 600 research or test reactors have been built throughout the world. Today 255 research reactors are operating in 57 countries and about 70% are over 25 years old. Whereas there are very few reactor types for power plants because of rationalization and standardisation, there is a great diversity of research reactors. We can divide them into 2 groups: heavy water cooled reactors and light water moderated reactors. Heavy water cooled reactors are dedicated to the production of high flux of thermal neutrons which are extracted from the core by means of neutronic channels. Light water moderated reactors involved pool reactors and slightly pressurized closed reactors, they are polyvalent but their main purposes are material testing, technological irradiations, radionuclide production and neutron radiography. At the moment 8 research reactors are being built in Canada, Germany, Iran, Japan, Kazakhstan, Morocco, Russia and Slovakia and 8 others are planned in 7 countries (France, Indonesia, Nigeria, Russia, Slovakia, Thailand and Tunisia. Different research reactors are described: Phebus, Masurca, Phenix and Petten HFR. The general principles of nuclear safety applied to test reactors are presented. (A.C.)

  1. NF-κB/AP-1-Targeted Inhibition of Macrophage-Mediated Inflammatory Responses by Depigmenting Compound AP736 Derived from Natural 1,3-Diphenylpropane Skeleton

    Directory of Open Access Journals (Sweden)

    Van Thai Ha

    2014-01-01

    Full Text Available AP736 was identified as an antimelanogenic drug that can be used for the prevention of melasma, freckles, and dark spots in skin by acting as a suppressor of melanin synthesis and tyrosinase expression. Since macrophage-mediated inflammatory responses are critical for skin health, here we investigated the potential anti-inflammatory activity of AP736. The effects of AP736 on various inflammatory events such as nitric oxide (NO/prostaglandin (PG E2 production, inflammatory gene expression, phagocytic uptake, and morphological changes were examined in RAW264.7 cells. AP736 was found to strongly inhibit the production of both NO and PGE2 in lipopolysaccharide- (LPS- treated RAW264.7 cells. In addition, AP736 strongly inhibited both LPS-induced morphological changes and FITC-dextran-induced phagocytic uptake. Furthermore, AP736 also downregulated the expression of multiple inflammatory genes, such as inducible NO synthase (iNOS, cyclooxygenase- (COX- 2, and interleukin- (IL- 1β in LPS-treated RAW264.7 cells. Transcription factor analysis, including upstream signalling events, revealed that both NF-κB and AP-1 were targeted by AP736 via inhibition of the IKK/IκBα and IRAK1/TAK1 pathways. Therefore, our results strongly suggest that AP736 is a potential anti-inflammatory drug due to its suppression of NF-κB-IKK/IκBα and AP-1-IRAK1/TAK1 signalling, which may make AP736 useful for the treatment of macrophage-mediated skin inflammation.

  2. Research progress on assessment of reactor vessel integrity under severe accident conditions

    International Nuclear Information System (INIS)

    As a representative method of reactor vessel integrity (RVI) under severe accident conditions, In-vessel retention of molten core debris (IVR) is an important severe accident management strategy employed in the AP1000 generation-3 Pressurized Water Reactor. In this paper, research progress on the test and theoretical analysis based on RVI is reviewed. Test facilities and techniques, as well as the modeling are summarized. In addition, tools for numerical simulation for RVI are evaluated. Finally, based on the applications in thermal hydraulic technology for the generation-3 Pressurized Water Reactor in China, the potential research direction of thermal-hydraulics under RVI conditions are discussed. (authors)

  3. Molecular Basis for Enhancement of the Meiotic DMCI Recombinase by RAD51AP1

    Energy Technology Data Exchange (ETDEWEB)

    Dray, Eloise; Dunlop, Myun Hwa; Kauppi, Liisa; San Filippo, Joseph San; Wiese, Claudia; Tsai, Miaw-Sheue; Begovic, Sead; Schild, David; Jasin, Maria; Keeney, Scott; Sung, Patrick

    2010-11-05

    Homologous recombination is needed for meiotic chromosome segregation, genome maintenance, and tumor suppression. RAD51AP1 (RAD51 Associated Protein 1) has been shown to interact with and enhance the recombinase activity of RAD51. Accordingly, genetic ablation of RAD51AP1 leads to enhanced sensitivity to and also chromosome aberrations upon DNA damage, demonstrating a role for RAD51AP1 in mitotic homologous recombination. Here we show physical association of RAD51AP1 with the meiosis-specific recombinase DMC1 and a stimulatory effect of RAD51AP1 on the DMC1-mediated D-loop reaction. Mechanistic studies have revealed that RAD51AP1 enhances the ability of the DMC1 presynaptic filament to capture the duplex DNA partner and to assemble the synaptic complex, in which the recombining DNA strands are homologously aligned. We also provide evidence that functional co-operation is dependent on complex formation between DMC1 and RAD51AP1, and that distinct epitopes in RAD51AP1 mediate interactions with RAD51 and DMC1. Finally, we show that RAD51AP1 is expressed in mouse testes, and that RAD51AP1 foci co-localize with a subset of DMC1 foci in spermatocytes. These results suggest that RAD51AP1 also serves an important role in meiotic homologous recombination.

  4. Westinghouse Passive Plants - AP600 and S PWR

    International Nuclear Information System (INIS)

    The original thought behind the AP600 passive design was that if the U. S. nuclear industry was to be revitalized, it would require a new, advanced technology with clearly proven benefits in safety. Response from the international arena indicates that, regardless of local domestic consideration, a revitalization of the U. S. industry is seen as very important, even essential, worldwide. And the potential for scale up of these passive safety features has been clearly established, allowing the benefits of the passive technology to be realized in countries that, for whatever reason, are interested in larger plant sizes only. Government projections indicate that U. S. energy demands in the 1990s will grow steadily, creating the need for approximately 117,000 to 322,000 MW of new generating capacity by the year 2010. Although this growth in electricity demand continues to be strong, orders for new nuclear power plants have not kept pace, in part due to licensing delays, prohibitive construction costs, and public uncertainty about safety. However, with the increased concerns about the environmental and economic security risks involved with an excessive dependence on fossil fuels, there is a growing realization that nuclear power must play a major role in our energy future. Looking to the future, Westinghouse is developing the AP600, a simplified two-loop PWR featuring passive safety systems. Drawing on the results of the AP600 development and testing programs, Westinghouse is also developing the larger S PWR, a passive, three-loop power plant with an output in the 900 to 1000 MW range

  5. Phenomena identification and ranking tables for Westinghouse AP600 small break loss-of-coolant accident, main steam line break, and steam generator tube rupture scenarios

    International Nuclear Information System (INIS)

    This report revision incorporates new experimental evidence regarding AP600 behavior during small break loss-of-coolant accidents. This report documents the results of Phenomena Identification and Ranking Table (PIRT) efforts for the Westinghouse AP600 reactor. The purpose of this PIRT is to identify important phenomena so that they may be addressed in both the experimental programs and the RELAP5/MOD3 systems analysis computer code. In Revision of this report, the responses of AP600 during small break loss-of-coolant accident, main steam line break, and steam generator tube rupture accident scenarios were evaluated by a committee of thermal-hydraulic experts. Committee membership included Idaho National Engineering and Environmental Laboratory staff and recognized thermal-hydraulic experts from outside of the laboratory. Each of the accident scenarios was subdivided into separate, sequential periods or phases. Within each phase, the plant behavior is controlled by, at most, a few thermal-hydraulic processes. The committee identified the phenomena influencing those processes, and ranked ampersand influences as being of high, medium, low, or insignificant importance. The primary product of this effort is a series of tables, one for each phase of each accident scenario, describing the thermal-hydraulic phenomena judged by the committee to be important, and the relative ranking of that importance. The rationales for the phenomena selected and their rankings are provided. This document issue incorporates an update of the small break loss-of-coolant accident portion of the report. This revision is the result of the release of experimental evidence from AP600-related integral test facilities (ROSA/AP600, OSU, and SPES) and thermal-hydraulic expert review. The activities associated with this update were performed during the period from June 1995 through November 1996. 8 refs., 26 figs., 42 tabs

  6. Phenomena identification and ranking tables for Westinghouse AP600 small break loss-of-coolant accident, main steam line break, and steam generator tube rupture scenarios

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, G.E.; Fletcher, C.D.; Davis, C.B. [and others

    1997-06-01

    This report revision incorporates new experimental evidence regarding AP600 behavior during small break loss-of-coolant accidents. This report documents the results of Phenomena Identification and Ranking Table (PIRT) efforts for the Westinghouse AP600 reactor. The purpose of this PIRT is to identify important phenomena so that they may be addressed in both the experimental programs and the RELAP5/MOD3 systems analysis computer code. In Revision of this report, the responses of AP600 during small break loss-of-coolant accident, main steam line break, and steam generator tube rupture accident scenarios were evaluated by a committee of thermal-hydraulic experts. Committee membership included Idaho National Engineering and Environmental Laboratory staff and recognized thermal-hydraulic experts from outside of the laboratory. Each of the accident scenarios was subdivided into separate, sequential periods or phases. Within each phase, the plant behavior is controlled by, at most, a few thermal-hydraulic processes. The committee identified the phenomena influencing those processes, and ranked & influences as being of high, medium, low, or insignificant importance. The primary product of this effort is a series of tables, one for each phase of each accident scenario, describing the thermal-hydraulic phenomena judged by the committee to be important, and the relative ranking of that importance. The rationales for the phenomena selected and their rankings are provided. This document issue incorporates an update of the small break loss-of-coolant accident portion of the report. This revision is the result of the release of experimental evidence from AP600-related integral test facilities (ROSA/AP600, OSU, and SPES) and thermal-hydraulic expert review. The activities associated with this update were performed during the period from June 1995 through November 1996. 8 refs., 26 figs., 42 tabs.

  7. Nuclear reactor building

    International Nuclear Information System (INIS)

    Purpose: To prevent seismic vibrations of external buildings from transmitting to the side walls of a reactor container in a tank type FBR reactor building. Constitution: The reactor building is structured such that the base mat for a reactor container chamber and a reactor container is separated from the base mat for the walls of building, and gas-tight material such as silicon rubber is filled in the gap therebetween. With such a constitution, even if the crane-supporting wall vibrates violently upon occurrence of earthqualkes, the seismic vibrations do not transmit toward the reactor container chamber. (Horiuchi, T.)

  8. Euphorbesulins A-P, Structurally Diverse Diterpenoids from Euphorbia esula.

    Science.gov (United States)

    Zhou, Bin; Wu, Yan; Dalal, Seema; Cassera, Maria B; Yue, Jian-Min

    2016-08-26

    Aqueous ethanol extracts of powdered twigs of Euphorbia esula afforded 16 new diterpenoids, named euphorbesulins A-P. These euphorbesulins included presegetane (1-3), jatrophane (4-14), paraliane (15), and isopimarane (16) diterpenoids as well as six known analogues. Compounds 1-3 represent a rare type of presegetane diterpenoid. Their structures were determined by analysis of the spectroscopic data, and the absolute configuration of 1 was established by X-ray crystallography. Diterpenoid 7 showed low nanomolar antimalarial activity, while the remaining compounds showed only moderate or no antimalarial activity. PMID:27447736

  9. COMMIX analysis of AP-600 Passive Containment Cooling System

    International Nuclear Information System (INIS)

    COMMIX modeling and basic concepts that relate components, i.e., containment, water film cooling, and natural draft air flow systems. of the AP-600 Passive Containment Cooling System are discussed. The critical safety issues during a postulated accident have been identified as (1) maintaining the liquid film outside the steel containment vessel, (2) ensuring the natural convection in the air annulus. and (3) quantifying both heat and mass transfer accurately for the system. The lack of appropriate heat and mass transfer models in the present analysis is addressed. and additional assessment and validation of the proposed models is proposed

  10. Deionized water system design for the APS RF building

    International Nuclear Information System (INIS)

    The deionized (DI) water system design for the Advanced Photon Source (APS) radio frequency (RF) building is presented. The system is described by RF component specifications, limiting design parameters, hardware, monitoring equipment, and operating experience. Varying maximum/minimum specifications for flow rate, temperature, and pressure for the components are discussed. Similarities and differences between the five separate RF equipment stations are identified. The use of a supply and return manifold system at each station, which provides DI water to the equipment stations in a parallel arrangement, is described

  11. The driving mechanism of roAp stars

    International Nuclear Information System (INIS)

    We analyse in detail the driving mechanism of roAp stars and present the theoretical instability strip predicted by our models with solar metallicity. A particular attention is given to the interpretation of the role played by the different eigenfunctions in the stabilization of the modes at the red edge of the instability strip. The gradient of temperature in the HI opacity bump appears to play a major role in this context. We also consider the particular and complex role played by the shape of the eigenfunctions (location of the nodes, ...).

  12. Santiago Apóstol en la intimidad del santiaguero

    OpenAIRE

    Portuondo Zúñiga, Olga

    2010-01-01

    La relación entre el apóstol Santiago (el Mayor) y Santiago de Cuba remonta hasta el ya casi milenio de su fundación; y en el día de hoy, la ciudad está orgullosa de su nombre y de su patronazgo. La tradición engarza las cuentas de una historia común, sin que implique una plena identificación espiritual inicial, ni la inexistencia de escollos a salvar para que la comunidad asumiera como honra y nobleza su cualidad santiaguera.

  13. Salidas no documentadas y facturas apócrifas

    OpenAIRE

    Martin, María José

    2013-01-01

    En el presente trabajo analizaremos el instituto de salidas no documentadas reglado en los arts. 37 y 38 y normas concordantes de la Ley 20.628 de impuesto a las ganancias, en relación a su naturaleza jurídica, procedencia del cómputo de gastos, posibilidad de deducción de créditos fiscales, la viabilidad de su aplicación al caso de comprobantes apócrifos o incompletos, los pronunciamientos judiciales relacionados y las consecuencias en el ámbito penal.

  14. AP1000 PSA model and its model format conversion

    International Nuclear Information System (INIS)

    The probabilistic safety assessment (PSA) model of the third generation nuclear power technology (AP1000) is built with CAFTA code, while the RiskSpectrum code is used in our institute. Based on the analysis of the data files of the two codes, the conversion code CAFTA2RS is developed to extract information from the PSA model built with CAFTA, modify the data format that incompatible with RiskSpectrum, convert the gate type, such as AANB, EQU and so on, to the gate type acceptable with RS, and finally convert the PSA model from the format of CAFTA code to the format of RiskSpectrum code automatically. (authors)

  15. Updated TRAC analysis of an 80% double-ended cold-leg break for the AP600 design

    International Nuclear Information System (INIS)

    An updated TRAC 80% large-break loss-of-coolant accident (LBLOCA) has been calculated for the Westinghouse AP600 advanced reactor design, The updated calculation incorporates major code error corrections, model corrections, and plant design changes. The 80% break size was calculated by Westinghouse to be the most severe large-break size for the AP600 design. The LBLOCA transient was calculated to 144 s. Peak cladding temperatures (PCTS) were well below the Appendix K limit of 1,478 K (2,200 F), but very near the cladding oxidation temperature of 1,200 K (1,700 F). Transient event times and PCT for the TRAC calculation were in reasonable agreement with those calculated by Westinghouse using their WCOBRA/TRAC code. However, there were significant differences in the detailed phenomena calculated by the two codes, particularly during the blowdown phase. The reasons for these differences are still being investigated. Additional break sizes and break locations need to be analyzed to confirm the most severe break postulated by Westinghouse

  16. Reactor Physics Programme

    International Nuclear Information System (INIS)

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies

  17. Constitutive Expression of Sense & Antisense PtAP3, an AP3 Homologue Gene of Populus tomentosa, Affects Growth and Flowering Time in Transgenic Tobacco

    Institute of Scientific and Technical Information of China (English)

    2005-01-01

    To analyze the function of PtAP3, an APETALA3 (AP3) homologue gene isolated from Populus tomentosa Carr., the full length sequence (1 797 bp) and a fragment (870 bp) of PtAP3 were fused to a CaMV 35S promoter of pBI121 to generate the sense and antisense constructs of PtAP3. These constructs were transformed into tobacco by Agrobacterium infection of leaf disks and selection on kanamycin medium. Some sense and antisense transgenic tobacco plants were obtained by PCR and Southern blot analysis. Great phenotypic differences in transgenic tobacco plants were observed. Almost all of sense PtAP3 to transgenic tobaccos showed a higher growth rate than those of antisense transformants and a few developed pregnancy earlier than wild type seedlings and antisense transformants under the same conditions.

  18. Ship propulsion reactors technology

    International Nuclear Information System (INIS)

    This paper takes the state of the art on ship propulsion reactors technology. The french research programs with the corresponding technological stakes, the reactors specifications and advantages are detailed. (A.L.B.)

  19. Undergraduate reactor control experiment

    International Nuclear Information System (INIS)

    A sequence of reactor and related experiments has been a central element of a senior-level laboratory course at Pennsylvania State University (Penn State) for more than 20 yr. A new experiment has been developed where the students program and operate a computer controller that manipulates the speed of a secondary control rod to regulate TRIGA reactor power. Elementary feedback control theory is introduced to explain the experiment, which emphasizes the nonlinear aspect of reactor control where power level changes are equivalent to a change in control loop gain. Digital control of nuclear reactors has become more visible at Penn State with the replacement of the original analog-based TRIGA reactor control console with a modern computer-based digital control console. Several TRIGA reactor dynamics experiments, which comprise half of the three-credit laboratory course, lead to the control experiment finale: (a) digital simulation, (b) control rod calibration, (c) reactor pulsing, (d) reactivity oscillator, and (e) reactor noise

  20. Process heat reactors

    International Nuclear Information System (INIS)

    The consumption of heat, for industrial and domestic needs, takes up half of the national energy supply; direct utilization of the heat produced by nuclear reactors could therefore contribute to reduce the deficit in the energetic results. The restraints proper to heat consumption (dispersal and variety of consumers, irregular demand) involve the development of the heat transport system structures and adequate nuclear reactors. With this in view, the Commissariat a l'Energie Atomique and Technicatome are developing the CAS reactor series, pressurized water reactors (PWR), (CAS 3G reactor with a power of 420 MW.th.), and the Thermos reactor (100 MW.th.), directly conceived to produce heat at 1200C and whose technology derives from the experimental pool reactors type. In order to prove the value of the Thermos design, an experimental reactor should soon be constructed in the Saclay nuclear research centre

  1. Reactor System Design

    International Nuclear Information System (INIS)

    SMART NPP(Nuclear Power Plant) has been developed for duel purpose, electricity generation and energy supply for seawater desalination. The objective of this project IS to design the reactor system of SMART pilot plant(SMART-P) which will be built and operated for the integrated technology verification of SMART. SMART-P is an integral reactor in which primary components of reactor coolant system are enclosed in single pressure vessel without connecting pipes. The major components installed within a vessel includes a core, twelve steam generator cassettes, a low-temperature self pressurizer, twelve control rod drives, and two main coolant pumps. SMART-P reactor system design was categorized to the reactor coe design, fluid system design, reactor mechanical design, major component design and MMIS design. Reactor safety -analysis and performance analysis were performed for developed SMART=P reactor system. Also, the preparation of safety analysis report, and the technical support for licensing acquisition are performed

  2. RAD51AP2, a novel vertebrate- and meiotic-specific protein, sharesa conserved RAD51-interacting C-terminal domain with RAD51AP1/PIR51

    Energy Technology Data Exchange (ETDEWEB)

    Kovalenko, Oleg V.; Wiese, Claudia; Schild, David

    2006-07-25

    Many interacting proteins regulate and/or assist the activities of RAD51, a recombinase which plays a critical role in both DNA repair and meiotic recombination. Yeast two-hybrid screening of a human testis cDNA library revealed a new protein, RAD51AP2 (RAD51 Associated Protein 2), that interacts strongly with RAD51. A full-length cDNA clone predicts a novel vertebrate specific protein of 1159 residues, and the RAD51AP2 transcript was observed only in meiotic tissue (i.e. adult testis and fetal ovary), suggesting a meiotic-specific function for RAD51AP2. In HEK293 cells the interaction of RAD51 with an ectopically-expressed recombinant large fragment of RAD51AP2 requires the C-terminal 57 residues of RAD51AP2. This RAD51-binding region shows 81% homology to the C-terminus of RAD51AP1/PIR51, an otherwise totally unrelated RAD51-binding partner that is ubiquitously expressed. Analyses using truncations and point mutations in both RAD51AP1 and RAD51AP2 demonstrate that these proteins use the same structural motif for RAD51 binding. RAD54 shares some homology with this RAD51-binding motif, but this homologous region plays only an accessory role to the adjacent main RAD51-interacting region, which has been narrowed here to 40 amino acids. A novel protein, RAD51AP2, has been discovered that interacts with RAD51 through a C-terminal motif also present in RAD51AP1.

  3. Duplication of AP1 within the Spinacia oleracea L. AP1/FUL clade is followed by rapid amino acid and regulatory evolution.

    Science.gov (United States)

    Sather, D Noah; Golenberg, Edward M

    2009-02-01

    The AP1/FUL clade of MADS box genes have undergone multiple duplication events among angiosperm species. While initially identified as having floral meristem identity and floral organ identity function in Arabidopsis, the role of AP1 homologs does not appear to be universally conserved even among eudicots. In comparison, the role of FRUITFULL has not been extensively explored in non-model species. We report on the isolation of three AP1/FUL genes from cultivated spinach, Spinacia oleracea L. Two genes, designated SpAPETALA1-1 (SpAP1-1) and SpAPETALA1-2 (SpAP1-2), cluster as paralogous genes within the Caryophyllales AP1 clade. They are highly differentiated in the 3', carboxyl-end encoding region of the gene following the third amphipathic alpha-helix region, while still retaining some elements of a signature AP1 carboxyl motifs. In situ hybridization studies also demonstrate that the two paralogs have evolved different temporal and spatial expression patterns, and that neither gene is expressed in the developing sepal whorl, suggesting that the AP1 floral organ identity function is not conserved in spinach. The spinach FRUITFULL homolog, SpFRUITFULL (SpFUL), has retained the conserved motif and groups with Caryophyllales FRUITFULL homologs. SpFUL is expressed in leaf as well as in floral tissue, and shows strong expression late in flower development, particularly in the tapetal layer in males, and in the endothecium layer and stigma, in the females. The combined evidence of high rates of non-synonymous substitutions and differential expression patterns supports a scenario in which the AP1 homologs in the spinach AP1/FUL gene family have experienced rapid evolution following duplication. PMID:19005675

  4. Particle velocity measurements in HVOF and APS systems

    International Nuclear Information System (INIS)

    Production of reliable, repeatable coatings requires precise control of the process used to deposit them. Significant advances have recently been made in controlling the inputs to thermal spray processes, however, much work remains to be done to control process outputs and to correlate these with coatings characteristics. Thermal spray processes comprise the heating/melting, acceleration, impact, rapid solidification and incremental build-up of a large number of individual particles. Particle velocity is a key process parameter in determining coating properties such as density/porosity, bond strength and residual stress. Laser Stroboscopy and optical image analysis techniques have been used to image particles traveling in high velocity oxy-fuel (HVOF) and air plasma spray (APS) jets. Results indicate that these techniques can be used to measure particle velocity, trajectory and velocity distribution(s) in thermal spray jets. mean particle velocities of ∼400 m/s and ∼100 m/s have been measured for HVOF and APS respectively

  5. Luteolin, a flavonoid, inhibits AP-1 activation by basophils

    International Nuclear Information System (INIS)

    Flavonoids including luteolin, apigenin, and fisetin are inhibitors of IL-4 synthesis and CD40 ligand expression by basophils. This study was done to search for compounds with greater inhibitory activity of IL-4 expression and to clarify the molecular mechanisms through which flavonoids inhibit their expression. Of the 37 flavonoids and related compounds examined, ayanin, luteolin, and apigenin were the strongest inhibitors of IL-4 production by purified basophils in response to anti-IgE antibody plus IL-3. Luteolin did not suppress Syk or Lyn phosphorylation in basophils, nor did suppress p54/46 SAPK/JNK, p38 MAPK, and p44/42 MAPK activation by a basophilic cell line, KU812 cells, stimulated with A23187 and PMA. However, luteolin did inhibit phosphorylation of c-Jun and DNA binding activity of AP-1 in nuclear lysates from stimulated KU812 cells. These results provide a fundamental structure of flavonoids for IL-4 inhibition and demonstrate a novel action of flavonoids that suppresses the activation of AP-1

  6. High-brightness beam diagnostics for the APS linac

    International Nuclear Information System (INIS)

    The Advanced Photon Source (APS) injector includes an S-band linac with the capability to accelerate beams to 650 MeV. The linac has recently been upgraded with the installation of an rf thermionic gun in addition to the standard DC thermionic gun. The rf gun is predicted to have lower emittance (5πmm mrad) and may be used to support the APS self-amplified spontaneous emission (SASE) experiments. The critical characterization of this gun's beam has begun with a beam diagnostics station at the end of the linac that can address beam transverse size, emittance, and bunch length (peak current). This station uses both an optical transition radiation (OTR) screen at 45 degree to the beam direction and a Ce-doped YAG single crystal normal to the beam with a 45 degree mirror behind it. The visible light images are detected by a Vicon CCD camera and a Hamamatsu C5680 synchroscan streak camera. Spatial resolution of about 30 microm (σ) and temporal resolution of 1 ps (σ) have been demonstrated. Examples of rf gun beam characterization at 220 MeV are reported

  7. Preparation of and porosity measurements on oxidic APS spray coatings; Praeparation und Porositaetsmessung an oxidischen APS-Spritzschichten

    Energy Technology Data Exchange (ETDEWEB)

    Motl, Wolfgang [H.C. Starck GmbH, Laufenburg (Germany); Schnarr, Holger [Struers GmbH, Willich (Germany)

    2015-07-01

    Zirconium oxide coatings for application in the field of turbine construction have to exhibit certain properties in order to meet high temperature requirements. One of the most important properties is the porosity, for it provides a thermal insulation of the coated material. For this reason, the porosity is routinely determined as quality parameter for spray coatings which helps determining their suitability for a particular application. The following work summarizes the results of the round robin test ''Preparation of and Porosity Measurements on Oxidic APS Spray Coatings'' by the DGM working group ''Preparation''.

  8. Nuclear Reactor RA Safety Report, Vol. 11, Reactor operation

    International Nuclear Information System (INIS)

    This volume includes the following chapters describing: Organisation of reactor operation (including operational safety, fuel management, and regulatory rules for RA reactor operation); Control and maintenance of reactor components (reactor core, nuclear fuel, heavy water and cover gas systems, mechanical structures, electric power supply system, reactor instrumentation); Quality assurance and Training of the reactor personnel

  9. The Chernobylsk reactor accident

    International Nuclear Information System (INIS)

    The construction, the safety philosophy, the major reactor physical parameters of RBMK-1000 type reactor units and the detailed description of the Chernobylsk-4 reactor accident, its causes and conclusions, the efforts to reduce the consequences on the reactor site and in the surroundings are discussed based on different types of Soviet documents including the report presented to the IAEA by the Soviet Atomic Energy Agency in August 1986. (V.N.)

  10. Zero energy reactor 'RB'

    International Nuclear Information System (INIS)

    In 1958 the zero energy reactor RB was built with the purpose of enabling critical experiments with various reactor systems to be carried out. The first core assembly built in this reactor consists of heavy water as moderator and natural uranium metal as fuel. In order to be able to obtain very accurate results when measuring the main characteristics of the assembly the reactor was built as a completely bare system. (author)

  11. Evolution and protein interactions of AP2 proteins in Brassicaceae: Evidence linking development and environmental responses.

    Science.gov (United States)

    Zeng, Liping; Yin, Yue; You, Chenjiang; Pan, Qianli; Xu, Duo; Jin, Taijie; Zhang, Bailong; Ma, Hong

    2016-06-01

    Plants have evolved a large number of transcription factors (TF), which are enriched among duplicate genes, highlighting their roles in complex regulatory networks. The APETALA2/EREBP-like genes constitute a large plant TF family and participate in development and stress responses. To probe the conservation and divergence of AP2/EREBP genes, we analyzed the duplication patterns of this family in Brassicaceae and identified interacting proteins of representative Arabidopsis AP2/EREBP proteins. We found that many AP2/EREBP duplicates generated early in Brassicaceae history were quickly lost, but many others were retained in all tested Brassicaceae species, suggesting early functional divergence followed by persistent conservation. In addition, the sequences of the AP2 domain and exon numbers were highly conserved in rosids. Furthermore, we used 16 A. thaliana AP2/EREBP proteins as baits in yeast screens and identified 1,970 potential AP2/EREBP-interacting proteins, with a small subset of interactions verified in planta. Many AP2 genes also exhibit reduced expression in an anther-defective mutant, providing a possible link to developmental regulation. The putative AP2-interacting proteins participate in many functions in development and stress responses, including photomorphogenesis, flower development, pathogenesis, drought and cold responses, abscisic acid and auxin signaling. Our results present the AP2/EREBP evolution patterns in Brassicaceae, and support a proposed interaction network of AP2/EREBP proteins and their putative interacting proteins for further study. PMID:26472270

  12. Induction of neural crest in Xenopus by transcription factor AP2alpha.

    Science.gov (United States)

    Luo, Ting; Lee, Young-Hoon; Saint-Jeannet, Jean-Pierre; Sargent, Thomas D

    2003-01-21

    We report experiments with Xenopus laevis, using both intact embryos and ectodermal explants, showing that the transcription factor AP2alpha is positively regulated by bone morphogenetic protein (BMP) and Wnt signaling, and that this activation is an essential step in the induction of neural crest (NC). Ectopic expression of AP2alpha is sufficient to activate high-level expression of NC-specific genes such as Slug and Sox9, which can occur as isolated domains within the neural plate as well as by expansion of endogenous NC territories. AP2alpha also has the property of inducing NC in isolated ectoderm in which Wnt signaling is provided but BMP signaling is minimized by overexpression of chordin. Like other NC regulatory factors, activation of AP2alpha requires some attenuation of endogenous BMP signaling; however, this process occurs at a lower threshold for AP2alpha. Furthermore, AP2alpha expression domains are larger than for other NC factors. Loss-of-function experiments with antisense AP2alpha morpholino oligonucleotides result in severe reduction in the NC territory. These results support a central role for AP2alpha in NC induction. We propose a model in which AP2alpha expression, along with inactivation of NC inhibitory factors such as Dlx3, establish a feedback loop comprising AP2alpha, Sox9, and Slug, leading to and maintaining NC specification. PMID:12511599

  13. High solids fermentation reactor

    Science.gov (United States)

    Wyman, Charles E.; Grohmann, Karel; Himmel, Michael E.; Richard, Christopher J.

    1993-01-01

    A fermentation reactor and method for fermentation of materials having greater than about 10% solids. The reactor includes a rotatable shaft along the central axis, the shaft including rods extending outwardly to mix the materials. The reactor and method are useful for anaerobic digestion of municipal solid wastes to produce methane, for production of commodity chemicals from organic materials, and for microbial fermentation processes.

  14. Fossil nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Maurette, M.

    1976-01-01

    The discussion of fossil nuclear reactors (the Oklo phenomenon) covers the earth science background, neutron-induced isotopes and reactor operating conditions, radiation-damage studies, and reactor modeling. In conclusion possible future studies are suggested and the significance of the data obtained in past studies is summarized. (JSR)

  15. Fusion reactor studies

    International Nuclear Information System (INIS)

    A review is given of fusion reactor systems studies, the objectives of these studies are outlined and some recent conceptual reactor designs are described. The need for further studies in greater depth is indicated so that progress towards a commercial fusion reactor may be consolidated. (U.K.)

  16. Reactor power measuring device

    International Nuclear Information System (INIS)

    The present invention provides a self-powered long detector having a sensitivity over the entire length of a reactor core as an entire control rod withdrawal range of a BWR type reactor, and a reactor power measuring device using a gamma ray thermometer which scarcely causes sensitivity degradation. That is, a hollow protection pipe is disposed passing through the reactor core from the outside of a reactor pressure vessel. The self-powered long detectors and the gamma ray thermometers are inserted and installed in the protection pipe. An average reactor power in an axial direction of the reactor relative to a certain position in the horizontal cross section of the reactor core is determined based on the power of the self-powered long detector over the entire length of the reactor core. Since the response of the self-powered detector relative to a local power change is rapid, the output is used as an input signal to a safety protection device of the reactor core. Further, a gamma ray thermometer secured in the reactor and having scarce sensitivity degradation is used instead of an incore travelling neutron monitor used for relative calibration of an existent neutron monitor secured in the reactor. (I.S.)

  17. Probability safety assessment of LOOP accident to molten salt reactor

    International Nuclear Information System (INIS)

    Background: Loss of offsite power (LOOP) is a possible accident to any type of reactor, and this accident can reflect the main idea of reactor safety design. Therefore, it is very important to conduct a study on probabilistic safety assessment (PSA) of the molten salt reactor that is under LOOP circumstance. Purpose: The aim is to calculate the release frequency of molten salt radioactive material to the core caused by LOOP, and find out the biggest contributor to causing the radioactive release frequency. Methods: We carried out the PSA analysis of the LOOP using the PSA process risk spectrum, and assumed that the primary circuit had no valve and equipment reliability data based on the existing mature power plant equipment reliability data. Results: Through the PSA analysis, we got the accident sequences of the release of radioactive material to the core caused by LOOP and its frequency. The results show that the release frequency of molten salt radioactive material to the core caused by LOOP is about 2×10-11/(reactor ·year), which is far below that of the AP1000 LOOP. In addition, through the quantitative analysis, we obtained the point estimation and interval estimation of uncertainty analysis, and found that the biggest contributor to cause the release frequency of radioactive material to the core is the reactor cavity cooling function failure. Conclusion: This study provides effective help for the design and improvement of the following molten salt reactor system. (authors)

  18. The flame structure of AP/HTPB sandwiches

    Science.gov (United States)

    Chorpening, Benjamin Todd

    2000-10-01

    Ultraviolet emission imaging experiments have been used to study the combustion of sandwiches of ammonium perchlorate (AP) and hydroxyl-terminated polybutadiene (HTPB) in nitrogen at pressures up to 32 atm, with binder layers from 50 to 450 mum in thickness. An ICCD camera system has been used to image the flame emission near 310 nm, and a backlighting technique has been developed that allows determination of the corresponding surface shape during combustion. The results indicate the AP/HTPB interface regression rate of IPDI cured samples undergoing low power (100W) laser-assisted deflagration is nearly independent of the binder thickness for binders thicker than 100 mum. The pressure exponent of the regression rate is 0.31 up to 15 atm, increasing with pressure from 15 to 32 atm. Two primary regimes of flame behavior have been identified: a split flame base regime which occurs with high Peclet and Damkohler numbers, and a merged flame base regime which occurs with low Peclet and Damkohler numbers. A secondary regime, exhibiting a "lifted" flame, occurs with low Damkohler numbers and high Peclet numbers. The ultraviolet flame emissions observed in the experiments show a correspondence with the fuel-rich region of the flame, as determined with a Schvab-Zeldovich model. This is reasonable since the primary sources of ultraviolet emission in the 305--315 nm region, electronically excited OH and the CO + O reaction, are dependent on fuel related species. The growth of the fuel-rich region with increasing Peclet number, predicted by the model, is qualitatively matched by the experimental results. The predicted shrinkage of the fuel-rich region when the binder layer is diluted with fine AP is also qualitatively matched by the experiments. Comparison of the experimental results with a single-reaction model with finite rate kinetics shows a weak qualitative agreement on the influence of Damkohler number. A large increase in Damkohler number (factor of 20) leads to a strong

  19. Characteristics of shigellosis outbreaks in the AP of Vojvodina

    Directory of Open Access Journals (Sweden)

    Đurić Predrag

    2009-01-01

    Full Text Available Introduction. Shigellosis causes around 165 million infections and around 1 million deaths in the world every year. Two thirds of both infections and deaths are among children younger than 10. Shigellosis mainly spreads by direct or indirect contact, but water- and food-borne outbreaks are not rare. Material and methods. A descriptive epidemiological method was used to analyse characteristics of shigellosis outbreaks in the AP of Vojvodina in the period 1979-2005. Results. During this period 9.083 shigellosis infections were registered, 51,9% of them in 202 shigellosis outbreaks. The leading way of transmission was contact, but water- and food-borne outbreaks were also detected. The average number of infections in contact outbreaks of shigellosis was small - 6.3 infections. The highest average is in water-borne outbreaks - 55.1. Most of the outbreaks were those occurring in families (47.5% and most of them were registered in august. Discussion. Shigellosis has been mandatory reported in the AP of Vojvodina since 1945 and results of outbreak investigation of this disease were analyzed since 1979. In the first half of this period water was the most common way of agent transmission in shigellosis outbreaks, but in recent 15 years the contact became the leading one. In the last 5 years there was no water-borne shigellosis outbreaks. Almost one third of all outbreaks were imported from Montenegro and Croatia by tourists coming back from those countries. Most of the outbreaks are small outbreaks occurring in families, primarily transmitted by contact. Outbreaks in facilities for care of disabled children and elders are also important. Sh. sonnei and Sh. flexneri are the two serotypes identified, the former in 57.4% and the latter in 40.1% outbreaks. Conclusion. Shigellosis is a disease occurring in the AP of Vojvodina primarily in small outbreaks inside families, transmitted by contact, most often in August and more often caused by Sh. sonnei. Health

  20. Light water reactor safety

    CERN Document Server

    Pershagen, B

    2013-01-01

    This book describes the principles and practices of reactor safety as applied to the design, regulation and operation of light water reactors, combining a historical approach with an up-to-date account of the safety, technology and operating experience of both pressurized water reactors and boiling water reactors. The introductory chapters set out the basic facts upon which the safety of light water reactors depend. The central section is devoted to the methods and results of safety analysis. The accidents at Three Mile Island and Chernobyl are reviewed and their implications for light wate

  1. Nuclear reactor repairing device

    International Nuclear Information System (INIS)

    Purpose: To enable free repairing of an arbitrary position in an LMFBR reactor. Constitution: A laser light emitted from a laser oscillator installed out of a nuclear reactor is guided into a portion to be repaired in the reactor by using a reflecting mirror, thereby welding or cutting it. The guidance of the laser out of the reactor into the reactor is performed by an extension tube depending into a through hole of a rotary plug, and the guidance of the laser light into a portion to be repaired is performed by the transmitting and condensing action of the reflecting mirror. (Kamimura, M.)

  2. Fundamentals of reactor chemistry

    International Nuclear Information System (INIS)

    In the Nuclear Engineering School of JAERI, many courses are presented for the people working in and around the nuclear reactors. The curricula of the courses contain also the subject material of chemistry. With reference to the foreign curricula, a plan of educational subject material of chemistry in the Nuclear Engineering School of JAERI was considered, and the fundamental part of reactor chemistry was reviewed in this report. Since the students of the Nuclear Engineering School are not chemists, the knowledge necessary in and around the nuclear reactors was emphasized in order to familiarize the students with the reactor chemistry. The teaching experience of the fundamentals of reactor chemistry is also given. (author)

  3. Nuclear reactor physics

    CERN Document Server

    Stacey, Weston M

    2010-01-01

    Nuclear reactor physics is the core discipline of nuclear engineering. Nuclear reactors now account for a significant portion of the electrical power generated worldwide, and new power reactors with improved fuel cycles are being developed. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. The second edition of this successful comprehensive textbook and reference on basic and advanced nuclear reactor physics has been completely updated, revised and enlarged to include the latest developme

  4. Differential recognition of a dileucine-based sorting signal by AP-1 and AP-3 reveals a requirement for both BLOC-1 and AP-3 in delivery of OCA2 to melanosomes

    OpenAIRE

    Sitaram, Anand; Dennis, Megan K.; Chaudhuri, Rittik; De Jesus-Rojas, Wilfredo; Tenza, Danièle; Setty, Subba Rao Gangi; Wood, Christopher S.; Sviderskaya, Elena V.; Bennett, Dorothy C.; Raposo, Graça; Bonifacino, Juan S.; Marks, Michael S.

    2012-01-01

    Cell types that generate unique lysosome-related organelles (LROs), such as melanosomes in melanocytes, populate nascent LROs with cargoes that are diverted from endosomes. Cargo sorting toward melanosomes correlates with binding via cytoplasmically exposed sorting signals to either heterotetrameric adaptor AP-1 or AP-3. Some cargoes bind both adaptors, but the relative contribution of each adaptor to cargo recognition and their functional interactions with other effectors during transport to...

  5. Generation III+ Reactor Portfolio

    International Nuclear Information System (INIS)

    While the power generation needs of utilities are unique and diverse, they are all faced with the double challenge of meeting growing electricity needs while curbing CO2 emissions. To answer these diverse needs and help tackle this challenge, AREVA has developed several reactor models which are briefly described in this document: The EPRTM Reactor: designed on the basis of the Konvoi (Germany) and N4 (France) reactors, the EPRTM reactor is an evolutionary model designed to achieve best-in-class safety and operational performance levels. The ATMEA1TM reactor: jointly designed by Mitsubishi Heavy Industries and AREVA through ATMEA, their common company. This reactor design benefits from the competencies and expertise of the two mother companies, which have commissioned close to 130 reactor units. The KERENATM reactor: Designed on the basis of the most recent German BWR reactors (Gundremmingen) the KERENATM reactor relies on proven technology while also including innovative, yet thoroughly tested, features. The optimal combination of active and passive safety systems for a boiling water reactor achieves a very low probability of severe accident

  6. The Maple reactor project

    International Nuclear Information System (INIS)

    MDS Nordion supplies the majority of the world's reactor-produced medical isotopes. These isotopes are currently produced in the NRU reactor at AECL's Chalk River Laboratories (CRL). Medical isotopes and related technology are relied upon around the world to prevent, diagnose and treat disease. The NRU reactor, which has played a key role in supplying medical isotopes to date, has been in operation for over 40 years. Replacing this aging reactor has been a priority for MDS Nordion to assure the global nuclear medicine community that Canada will continue to be a dependable supplier of medical isotopes. MDS Nordion contracted AECL to construct two MAPLE reactors dedicated to the production of medical isotopes. The MDS Nordion Medical Isotope Reactor (MMIR) project started in September 1996. This paper describes the MAPLE reactors that AECL has built at its CRL site, and will operate for MDS Nordion. (author)

  7. High temperature reactors

    International Nuclear Information System (INIS)

    With the advent of high temperature reactors, nuclear energy, in addition to producing electricity, has shown enormous potential for the production of alternate transport energy carrier such as hydrogen. High efficiency hydrogen production processes need process heat at temperatures around 1173-1223 K. Bhabha Atomic Research Centre (BARC), is currently developing concepts of high temperature reactors capable of supplying process heat around 1273 K. These reactors would provide energy to facilitate combined production of hydrogen, electricity, and drinking water. Compact high temperature reactor is being developed as a technology demonstrator for associated technologies. Design has been also initiated for a 600 MWth innovative high temperature reactor. High temperature reactor development programme has opened new avenues for research in areas like advanced nuclear fuels, high temperature and corrosion resistant materials and protective coatings, heavy liquid metal coolant technologies, etc. The paper highlights design of these reactors and their material related requirements

  8. Spinning fluids reactor

    Science.gov (United States)

    Miller, Jan D; Hupka, Jan; Aranowski, Robert

    2012-11-20

    A spinning fluids reactor, includes a reactor body (24) having a circular cross-section and a fluid contactor screen (26) within the reactor body (24). The fluid contactor screen (26) having a plurality of apertures and a circular cross-section concentric with the reactor body (24) for a length thus forming an inner volume (28) bound by the fluid contactor screen (26) and an outer volume (30) bound by the reactor body (24) and the fluid contactor screen (26). A primary inlet (20) can be operatively connected to the reactor body (24) and can be configured to produce flow-through first spinning flow of a first fluid within the inner volume (28). A secondary inlet (22) can similarly be operatively connected to the reactor body (24) and can be configured to produce a second flow of a second fluid within the outer volume (30) which is optionally spinning.

  9. Research Update: Atmospheric pressure spatial atomic layer deposition of ZnO thin films: Reactors, doping, and devices

    Energy Technology Data Exchange (ETDEWEB)

    Hoye, Robert L. Z., E-mail: rlzh2@cam.ac.uk, E-mail: jld35@cam.ac.uk; MacManus-Driscoll, Judith L., E-mail: rlzh2@cam.ac.uk, E-mail: jld35@cam.ac.uk [Department of Materials Science and Metallurgy, University of Cambridge, 27 Charles Babbage Road, Cambridge CB3 0FS (United Kingdom); Muñoz-Rojas, David [LMGP, University Grenoble-Alpes, CNRS, F-3800 Grenoble (France); Nelson, Shelby F. [Kodak Research Laboratories, Eastman Kodak Company, Rochester, New York 14650 (United States); Illiberi, Andrea; Poodt, Paul [Holst Centre/TNO Thin Film Technology, Eindhoven, 5656 AE (Netherlands); Roozeboom, Fred [Holst Centre/TNO Thin Film Technology, Eindhoven, 5656 AE (Netherlands); Department of Applied Physics, Eindhoven University of Technology, P.O. Box 513, Eindhoven, 5600 MB (Netherlands)

    2015-04-01

    Atmospheric pressure spatial atomic layer deposition (AP-SALD) has recently emerged as an appealing technique for rapidly producing high quality oxides. Here, we focus on the use of AP-SALD to deposit functional ZnO thin films, particularly on the reactors used, the film properties, and the dopants that have been studied. We highlight how these films are advantageous for the performance of solar cells, organometal halide perovskite light emitting diodes, and thin-film transistors. Future AP-SALD technology will enable the commercial processing of thin films over large areas on a sheet-to-sheet and roll-to-roll basis, with new reactor designs emerging for flexible plastic and paper electronics.

  10. Research Update: Atmospheric pressure spatial atomic layer deposition of ZnO thin films: Reactors, doping, and devices

    International Nuclear Information System (INIS)

    Atmospheric pressure spatial atomic layer deposition (AP-SALD) has recently emerged as an appealing technique for rapidly producing high quality oxides. Here, we focus on the use of AP-SALD to deposit functional ZnO thin films, particularly on the reactors used, the film properties, and the dopants that have been studied. We highlight how these films are advantageous for the performance of solar cells, organometal halide perovskite light emitting diodes, and thin-film transistors. Future AP-SALD technology will enable the commercial processing of thin films over large areas on a sheet-to-sheet and roll-to-roll basis, with new reactor designs emerging for flexible plastic and paper electronics

  11. Measurement of sextupole orbit offsets in the APS storage ring

    International Nuclear Information System (INIS)

    Horizontal orbit errors at the sextuples in the Advanced Photon Source (APS) storage ring can cause changes in tune and modulation of the beta functions around the ring. To determine the significance of these effects requires knowing the orbit relative to the magnetic center of the sextuples. The method considered here to determine the horizontal beam position in a given sextupole is to measure the tune shift caused by a change in the sextupole strength. The tune shift and a beta function for the same plane uniquely determine the horizontal beam position in the sextupole. The beta function at the sextupole was determined by propagating the beta functions measured at nearby quadrupoles to the sextupole location. This method was used to measure the sextupole magnetic center offset relative to an adjacent beam position monitor (BPM) at a number of sextupole locations. We report on the successes and problems of the method as well as an improved method

  12. Improved temperature regulation of APS linac RF components

    International Nuclear Information System (INIS)

    The temperature of the APS S-Band linac's high-power rf components is regulated by water from individual closed-loop deionized (DI) water systems. The rf components are all made of oxygen-free high-conductivity copper and respond quickly to temperature changes. The SLED cavities are especially temperature-sensitive and cause beam energy instabilities when the temperature is not well regulated. Temperature regulation better than ± 0.1 F is required to achieve good energy stability. Improvements in the closed-loop water systems have enabled them to achieve a regulation of ± 0.05 F over long periods. Regulation philosophy and equipment are discussed and numerical results are presented

  13. Global coupling and decoupling of the APS storage ring

    Energy Technology Data Exchange (ETDEWEB)

    Chae, Y.C.; Liu, J.; Teng, L.C.

    1993-07-01

    This paper describes a study of controlling the coupling between the horizontal and the vertical betatron oscillations in the 7-GeV Advanced Photon Source (APS) storage ring. First, we investigate the strengthening of coupling using two families of skew quadrupoles. Twenty skew quadrupoles are arranged in the 40 sectors of the storage ring and powered in such a way so as to generate both quadrature components of the required 21st harmonic. The numerical results from tracking a single particle are presented for the various configurations of skew quadrupoles. Second, we describe the global decoupling procedure to minimize the unwanted coupling effects. These are mainly due to the random roll errors of normal quadruples. It is shown that even with the rather large rms roll error of 2 mrad, the coupling effects can be compensated for with 20 skew quadrupoles each having maximum strength one order of magnitude lower than the typical normal quadrupole strength.

  14. Hydrothermal waves in evaporating sessile drops (APS 2009)

    CERN Document Server

    Brutin, D; LeNiliot, C

    2009-01-01

    This fluid dynamics video was submitted to the Gallery of Fluid Motion for the 2009 APS Division of Fluid Dynamics Meeting in Minneapolis, Minnesota. Drop evaporation is a simple phenomena but still unclear concerning the mechanisms of evaporation. A common agreement of the scientific community based on experimental and numerical work evidences that most of the evaporation occurs at the triple line. However, the rate of evaporation is still empirically predicted due to the lack of knowledge on the convection cells which develop inside the drop under evaporation. The evaporation of sessile drop is more complicated than it appears due to the coupling by conduction with the heating substrate, the convection and conduction inside the drop and the convection and diffusion with the vapour phase. The coupling of heat transfer in the three phases induces complicated cases to solve even for numerical simulations. We present recent experimental fluid dynamics videos obtained using a FLIR SC-6000 coupled with a microsco...

  15. Counting statistics and loss corrections for the APS

    International Nuclear Information System (INIS)

    It has been suggested that for timing experiments, it might be advantageous to arrange the bunches in the storage ring in an asymmetrical mode. In this paper, we determine the counting losses from pulsed x-ray sources from basic probabilistic arguments and from Poisson statistics. In particular the impact on single photon counting losses of a variety of possible filling modes for the Advanced Photon Source (APS) is examined. For bunches of equal current, a loss of 10% occurs whenever the count rate exceeds 21% of the bunch repetition rate. This changes slightly when bunches containing unequal numbers of particles are considered. The results are applied to several common detector/electronics systems

  16. Towards a theory of rapidly oscillating Ap stars

    CERN Document Server

    Gough, Douglas

    2011-01-01

    Peculiar A stars are so named because they exhibit abundance peculiarities in their atmospheres. It is believed that these arise as a result of differentiation of chemical species in large magnetic spots in which convective mixing is inhibited: there might be just two antipodal spots, whose axis is inclined to the axis of rotation. Many of the Ap stars that are rotating slowly also pulsate, with periods substantially shorter than the period of the fundamental radial mode. The pulsations appear to be nonradial, but axisymmetric, with their common axis usually aligned with the axis of the spots. In this lecture I shall first discuss the magnetic suppression of convection in the spots, and then I shall try to explain the pulsation phenomenon, reviewing some of the suggestions that have been made to explain the alignment and the excitation mechanism, and finally raising some issues that need to be addressed.

  17. Commissioning results of the APS storage ring diagnostics systems

    International Nuclear Information System (INIS)

    Initial commissionings of the Advanced Photon Source (APS) 7-GeV storage ring and its diagnostics systems have been done. Early studies involved single-bunch measurements for beam transverse size (σx ∼ 150 μm, σy ∼ 50 μm), current, injection losses, and bunch length. The diagnostics have been used in studies related to the detection of an extra contribution to beam jitter at ∼ 6.5 Hz frequency; observation of bunch lengthening (σ ∼ 30 to 60 ps) with single-bunch current; observation of an induced vertical, head-tail instability; and detection of a small orbit change with insertion device gap position. More recently, operations at 100-mA stored-beam current, the baseline design goal, have been achieved with the support of beam characterizations

  18. An ancillary pumping system for the APS vacuum system

    Energy Technology Data Exchange (ETDEWEB)

    Walters, D.; Noonan, J.; Gagliano, J. [and others

    1997-06-01

    An ancillary pumping system has been designed and installed in the Advanced Photon Source (APS) storage ring. This vacuum system has the ability to pump sectors of the storage ring down from room pressure to ultra-high vacuum (UHV). The ancillary system is a {open_quotes}dry{close_quotes} system that uses a combination of turbomolecular pumps and oil-free roughing pumps. The benefits of this system are the reduction of equipment needed for in-tunnel maintenance, essential for the operation of a UHV storage ring; rapid response to vacuum emergencies and a guard to accidental exposures to hydrocarbon contamination. The operational logic and the pump interlock and controls are described.

  19. Thermal analysis of the crotch absorber in APS

    International Nuclear Information System (INIS)

    A crotch absorber design for use in the Advanced Photon source (APS) has been proposed and analyzed. the absorber is placed downstream of sectors S2 and S4 in the curved storage ring chamber and will be subjected to a peak power of 120 W/mm2 per 100mA synchrotron radiation. A beryllium ring is brazed on the GlidCop cooling cylinder in order to diffuse the concentrated bending magnet heating. One concentric water channel and two annular return water channels are arranged in the GlidCop cylinder to enhance the cooling. A Bodner-Partom thermoviscoplastic constitutive equation and a modified Manson-Coffin fatigue relation are proposed to simulate the cyclic thermal loading, as well as to predict the thermal fatigue life of the crotch absorber. Results of temperature and stress using finite element computations are displayed and series of e-beam welder tests and microstructure measurements are reported

  20. Cavity design and beam simulations for the APS rf gun

    International Nuclear Information System (INIS)

    An earlier note discussed the preliminary design of the 1-1/2 cell RF cavity for the APS RF gun. This note describes the final design, including cavity properties and simulation results from the program rf gun. The basic idea for the new design was that the successful SSRL design could be improved upon by reducing fields that had nonlinear dependence on radius. As discussed previously, this would reduce the emittance and produce tighter momentum and time distributions. In addition, it was desirable to increase the fields in the first half-cell relative to the fields in the second half-cell, in order to allow more rapid initial acceleration, which would reduce the effects of space charge. Both of these goals were accomplished in the new design

  1. Fabrication and Testing of Deflecting Cavities for APS

    Energy Technology Data Exchange (ETDEWEB)

    Mammosser, John; Wang, Haipeng; Rimmer, Robert; Jim, Henry; Katherine, Wilson; Dhakal, Pashupati; Ali, Nassiri; Jim, Kerby; Jeremiah, Holzbauer; Genfa, Wu; Joel, Fuerst; Yawei, Yang; Zenghai, Li

    2013-09-01

    Jefferson Lab (Newport News, Virginia) in collaboration with Argonne National Laboratory (Argonne, IL) has fabricated and tested four first article, 2.8 GHz, deflecting SRF cavities, for Argonne's Short-Pulse X-ray (SPX) project. These cavities are unique in many ways including the fabrication techniques in which the cavity cell and waveguides were fabricated. These cavity subcomponents were milled from bulk large grain niobium ingot material directly from 3D CAD files. No forming of sub components was used with the exception of the beam-pipes. The challenging cavity and helium vessel design and fabrication results from the stringent RF performance requirements required by the project and operation in the APS ring. Production challenges and fabrication techniques as well as testing results will be discussed in this paper.

  2. Progress on the development of APS beam position monitoring system

    International Nuclear Information System (INIS)

    This paper describes the development status of the beam position monitoring system for the Advanced Photon Source (APS), a third-generation light source now under construction at Argonne National Laboratory. The accelerator complex will consist of an electron linac, a positron linac, a positron accumulator ring (PAR), an injector synchrotron and a storage ring. For beam position measurement, striplines will be used on the linacs, while button-type pickups will be used on the injector synchrotron and the storage ring. A test stand with a prototype injector synchrotron beam position monitor (BPM) unit has been built, and we present the results of position calibration measurements using a wire. Comparison of the results with theoretical calculations will be presented. The current effort on similar storage ring BPM system measurements will also be discussed. 4 refs., 5 figs., 2 tabs

  3. Counting statistics and loss corrections for the APS

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Wah Keat; Mills, D.M.

    1991-07-01

    It has been suggested that for timing experiments, it might be advantageous to arrange the bunches in the storage ring in an asymmetrical mode. In this paper, we determine the counting losses from pulsed x-ray sources from basic probabilistic arguments and from Poisson statistics. In particular the impact on single photon counting losses of a variety of possible filling modes for the Advanced Photon Source (APS) is examined. For bunches of equal current, a loss of 10% occurs whenever the the count rate exceeds 21% of the bunch repetition rate. This changes slightly when bunches containing unequal numbers of particles are considered. The results are applied to several common detector/electronics systems. 3 refs., 5 figs., 1 tab.

  4. Quality Assurance Audit Practice in AP1000 Nuclear Project%AP1000核电工程的监查管理实践

    Institute of Scientific and Technical Information of China (English)

    张华

    2015-01-01

    文中主要介绍了AP1000核电工程三门、海阳依托项目建立质保体系所依据的标准、法规,和实施质保监查使用的主要方式方法.结合AP1000监查活动实施的现状,总结了AP1000核电工程的监查实践和经验,为其它核电工程的质量管理提供了建议和参考.

  5. Apurinic/apyrimidinic (AP) site recognition by the 5′-dRP/AP lyase in poly(ADP-ribose) polymerase-1 (PARP-1)

    OpenAIRE

    Khodyreva, S. N.; Prasad, R; Ilina, E. S.; Sukhanova, M. V.; Kutuzov, M. M.; Liu, Y.; Hou, E. W.; Wilson, S H; Lavrik, O. I.

    2010-01-01

    The capacity of human poly(ADP-ribose) polymerase-1 (PARP-1) to interact with intact apurinic/apyrimidinic (AP) sites in DNA has been demonstrated. In cell extracts, sodium borohydride reduction of the PARP-1/AP site DNA complex resulted in covalent cross-linking of PARP-1 to DNA; the identity of cross-linked PARP-1 was confirmed by mass spectrometry. Using purified human PARP-1, the specificity of PARP-1 binding to AP site-containing DNA was confirmed in competition binding experiments. PARP...

  6. Tank 241-AP-103 08/1999 Compatibility Grab Samples, Analytical Results for the Final Report

    International Nuclear Information System (INIS)

    This document is the format IV, final report for the tank 241-AP-103 (AP-103) grab samples taken in August 1999 to address waste compatibility concerns. Chemical, radiochemical, and physical analyses on the tank AP-103 samples were performed as directed in ''Compatibility Grub Sampling and Analysis Plan for Fiscal Year 1999'' (Sasaki 1999a). Any deviations from the instructions provided in the tank sampling and analysis plan (TSAP) were discussed in this narrative. No notification limits were exceeded

  7. HPV16 E6 and E6AP differentially cooperate to stimulate or augment Wnt signaling

    Energy Technology Data Exchange (ETDEWEB)

    Sominsky, Sophia, E-mail: sophia.tab@gmail.com [Department of Clinical Microbiology and Immunology, Sackler School of Medicine, Tel Aviv University, Tel Aviv 69978 (Israel); Kuslansky, Yael, E-mail: ykuslansky@gmail.com [Department of Clinical Microbiology and Immunology, Sackler School of Medicine, Tel Aviv University, Tel Aviv 69978 (Israel); Shapiro, Beny, E-mail: benyshap@gmail.com [Department of Clinical Microbiology and Immunology, Sackler School of Medicine, Tel Aviv University, Tel Aviv 69978 (Israel); Jackman, Anna, E-mail: jackman@post.tau.ac.il [Department of Clinical Microbiology and Immunology, Sackler School of Medicine, Tel Aviv University, Tel Aviv 69978 (Israel); Haupt, Ygal, E-mail: ygal.haupt@petermac.org [Research Division, The Peter MacCallum Cancer Centre, East Melbourne (Australia); Rosin-Arbesfeld, Rina, E-mail: arina@post.tau.ac.il [Department of Clinical Microbiology and Immunology, Sackler School of Medicine, Tel Aviv University, Tel Aviv 69978 (Israel); Sherman, Levana, E-mail: lsherman@post.tau.ac.il [Department of Clinical Microbiology and Immunology, Sackler School of Medicine, Tel Aviv University, Tel Aviv 69978 (Israel)

    2014-11-15

    The present study investigated the roles of E6 and E6AP in the Wnt pathway. We showed that E6 levels are markedly reduced in cells in which Wnt signaling is activated. Coexpression of wild-type or mutant E6AP (C820A) in Wnt-activated cells stabilized E6 and enhanced Wnt/β-catenin/TCF transcription. Expression of E6AP alone in nonstimulated cells elevated β-catenin level, promoted its nuclear accumulation, and activated β-catenin/TCF transcription. A knockdown of E6AP lowered β-catenin levels. Coexpression with E6 intensified the activities of E6AP. Further experiments proved that E6AP/E6 stabilize β-catenin by protecting it from proteasomal degradation. This function was dependent on the catalytic activity of E6AP, the kinase activity of GSK3β and the susceptibility of β-catenin to GSK3β phosphorylation. Thus, this study identified E6AP as a novel regulator of the Wnt signaling pathway, capable of cooperating with E6 in stimulating or augmenting Wnt/β-catenin signaling, thereby possibly contributing to HPV carcinogenesis. - Highlights: • The roles of E6 and E6AP in the Wnt pathway were investigated. • E6AP stabilizes E6 and enhances E6 activity in augmentation of Wnt signaling. • E6AP cooperates with E6 to stabilize β-catenin and stimulate Wnt/β-catenin signaling. • E6AP and E6 act through different mechanisms to augment or stimulate Wnt signaling.

  8. On the evolution of the magnetic field of Ap star $\\alpha^2$ CVn

    CERN Document Server

    Bychkov, V D; Madej, J; Topilskaya, G P

    2016-01-01

    New high-precision measurements of the longitudinal magnetic field of Ap stars suggest the existence of secular intrinsic variations of the global magnetic field in some stars. We argue that such changes are apparent in the Ap star $\\alpha^2$ CVn in the time scale of $\\sim$ 10 years, which results from the analysis of literature data. Therefore, such an observation implies, that the rate of magnetic field evolution of Ap stars is much higher than was previously thought.

  9. HPV16 E6 and E6AP differentially cooperate to stimulate or augment Wnt signaling

    International Nuclear Information System (INIS)

    The present study investigated the roles of E6 and E6AP in the Wnt pathway. We showed that E6 levels are markedly reduced in cells in which Wnt signaling is activated. Coexpression of wild-type or mutant E6AP (C820A) in Wnt-activated cells stabilized E6 and enhanced Wnt/β-catenin/TCF transcription. Expression of E6AP alone in nonstimulated cells elevated β-catenin level, promoted its nuclear accumulation, and activated β-catenin/TCF transcription. A knockdown of E6AP lowered β-catenin levels. Coexpression with E6 intensified the activities of E6AP. Further experiments proved that E6AP/E6 stabilize β-catenin by protecting it from proteasomal degradation. This function was dependent on the catalytic activity of E6AP, the kinase activity of GSK3β and the susceptibility of β-catenin to GSK3β phosphorylation. Thus, this study identified E6AP as a novel regulator of the Wnt signaling pathway, capable of cooperating with E6 in stimulating or augmenting Wnt/β-catenin signaling, thereby possibly contributing to HPV carcinogenesis. - Highlights: • The roles of E6 and E6AP in the Wnt pathway were investigated. • E6AP stabilizes E6 and enhances E6 activity in augmentation of Wnt signaling. • E6AP cooperates with E6 to stabilize β-catenin and stimulate Wnt/β-catenin signaling. • E6AP and E6 act through different mechanisms to augment or stimulate Wnt signaling

  10. The power of simplification: Operator interface with the AP1000R during design-basis and beyond design-basis events

    International Nuclear Information System (INIS)

    The AP1000R plant is an 1100-MWe pressurized water reactor with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance, safety and cost. The passive safety features are designed to function without safety-grade support systems such as component cooling water, service water, compressed air or HVAC. The AP1000 passive safety features achieve and maintain safe shutdown in case of a design-basis accident for 72 hours without need for operator action, meeting the expectations provided in the European Utility Requirements and the Utility Requirement Document for passive plants. Limited operator actions may be required to maintain safe conditions in the spent fuel pool (SFP) via passive means. This safety approach therefore minimizes the reliance on operator action for accident mitigation, and this paper examines the operator interaction with the Human-System Interface (HSI) as the severity of an accident increases from an anticipated transient to a design basis accident and finally, to a beyond-design-basis event. The AP1000 Control Room design provides an extremely effective environment for addressing the first 72 hours of design-basis events and transients, providing ease of information dissemination and minimal reliance upon operator actions. Symptom-based procedures including Emergency Operating Procedures (EOPs), Abnormal Operating Procedures (AOPs) and Alarm Response Procedures (ARPs) are used to mitigate design basis transients and accidents. Use of the Computerized Procedure System (CPS) aids the operators during mitigation of the event. The CPS provides cues and direction to the operators as the event progresses. If the event becomes progressively worse or lasts longer than 72 hours, and depending upon the nature of failures that may have occurred, minimal operator actions may be required outside of the control room in areas that have been designed to be accessible using components that have been designed to

  11. Reactor Safety: Introduction

    International Nuclear Information System (INIS)

    The programme of the Reactor Safety Division focuses on the development of expertise on materials behaviour under irradiation for fission and fusion oriented applications. Furthermore, as nuclear energy needs international public acceptance with respect to safety and efficient management of natural resources and wants to reduce the burden of nuclear waste, the Reactor Safety Division enhanced its efforts to develop the MYRRHA project. MYRRHA, an accelerator driven sub-critical system, might have the potential to cope in Europe with the above mentioned constraints on acceptability and might serve as a technological platform for GEN IV reactor development, in particular the Liquid Metal Fast Reactor.The Reactor Safety Division gathers three research entities that are internationally recognised: the Reactor Materials Research department, the Reactor Physics and MYRRHA department and the Instrumentation department.The objectives of Reactor Materials Research are: to evaluate the integrity and behaviour of structural materials and nuclear fuels used in present and future nuclear power industry; to perform research to unravel and understand the parameters that determine the material and fuel behaviour under or after irradiation; to contribute to the interpretation and modelling of the materials and fuels behaviour in order to develop and assess strategies for optimum life management of nuclear power plant components. The programmes within the Reactor Materials Research department concentrate on four distinct disciplines: Reactor Pressure Vessel Steel embrittlement Stress corrosion cracking in reactor coolant environment, including Irradiation Assisted Stress Corrosion Cracking; Nuclear Fuel characterisation and development of new fuel types for commercial and test reactors. Development of materials for Fusion and advanced nuclear fission reactors. The safe operation of present nuclear power plants relies primarily on the integrity of the reactor pressure vessel

  12. Piping stress analysis for AP600 secondary system

    International Nuclear Information System (INIS)

    Piping stress analysis for AP600 secondary system has been done using software PS-CAEPIPE version mainframe and CAEPIPE version PC. The loading applied to the system are statical load consist of deadweight, pressure load and thermal expansion load. Standard used in this calculation is ASME/ANSI B31.1. A piping system consists of pipes and appropriate components, such as achors, valves, pumps, flanges, etc. The parameters to be evaluated are pipe stress (psi), pipe displacements (in) and component loading (lbs). The use of support in the optimal manner is to be considered to reach a favorable condition. The allowable stress for sustained loads (death-weight and pressure) is SH (15000 psi in these cases) and for thermal load is SA (22500 psi in these cases). The allowable pipe displacement within 0.125 inches for total load. Therefore, the allowable load of components depends on the component itself. Three piping analysis packages for secondary system of AP600 have been done, those are HDS-310 (turbine building) and VYS-210 (auxiliary building). These system contain pipes with the diameter of 1 inch, 8 inches, 10 inches and 16 inches. The design pressures are in the range of 50 to 550 psi and the design temperatures are in the range of 185 deg F. The result shows that for analysis without supports, only CDS-080 is acceptable. After locating a variable support in HDS-310 and 3 rigid supports in VYS-210, all system are acceptable with the maximum pipe stress of 6533 psi, maximum displacement for sustained load of 0.069 inches and for total load of 0.635 inches

  13. The Dutch debate on reactor safety

    International Nuclear Information System (INIS)

    A survey is presented of the discussion on location sites for nuclear power plants in the Netherlands and the USA. It consists of two parts (A and B). This part (B) goes farther into the American reports already introduced briefly in part A. They are the reports of the IDCOR (nuclear power industry), ANS (American Nuclear Society), APS (American Physical Society), NRC (Nuclear Regulatory Commission) and UCS (Union of Concerned Scientists). Of each report a summary in English and an extended summary in Dutch is presented. Parts of the text of chapter 3 of the report 'Reactor accidents: the source term discussion' of the Technical University Twente (BC8501, 1985) are presented. 65 refs.; 15 figs.; 32 tabs

  14. Research and project practice in AP1000 nuclear plant MCR assemblies seismic test

    International Nuclear Information System (INIS)

    Background: The seismic test is one of Plant Equipment Seismic Qualification Methodologies. Purpose: To satisfy the special requirements of AP1000 seismic qualification, this test is not same to traditional seismic test. Methods: AP1000 nuclear plant equipment qualification has new methods and requirements. The special requirements as response spectrum, accelerometer installation and functional test are described for AP1000 MCR seismic test. Results: The test results are demonstrated that MCR assemblies are satisfied as AP1000 seismic qualification requirements. Conclusions: These requirements are beneficial to the qualification for structural integrity and functional safety. They are also used to find design margin. (authors)

  15. Isolation, classification and transcription profiles of the AP2/ERF transcription factor superfamily in citrus.

    Science.gov (United States)

    Xie, Xiu-lan; Shen, Shu-ling; Yin, Xue-ren; Xu, Qian; Sun, Chong-de; Grierson, Donald; Ferguson, Ian; Chen, Kun-song

    2014-07-01

    The AP2/ERF gene family encodes plant-specific transcription factors. In model plants, AP2/ERF genes have been shown to be expressed in response to developmental and environmental stimuli, and many function downstream of the ethylene, biotic, and abiotic stress signaling pathways. In citrus, ethylene is effective in regulation citrus fruit quality, such as degreening and aroma. However, information about the citrus AP2/ERF family is limited, and would enhance our understanding of fruit responses to environmental stress, fruit development and quality. CitAP2/ERF genes were isolated using the citrus genome database, and their expression patterns analyzed by real-time PCR using various orange organs and samples from a fruit developmental series. 126 sequences with homologies to AP2/ERF proteins were identified from the citrus genome, and, on the basis of their structure and sequence, assigned to the ERF family (102), AP2 family (18), RAV family (4) and Soloist (2). MEME motif analysis predicted the defining AP2/ERF domain and EAR repressor domains. Analysis of transcript accumulation in Citrus sinensis cv. 'Newhall' indicated that CitAP2/ERF genes show organ-specific and temporal expression, and provided a framework for understanding the transcriptional regulatory roles of AP2/ERF gene family members in citrus. Hierarchical cluster analysis and t tests identified regulators that potentially function during orange fruit growth and development. PMID:24566692

  16. AP Selection Algorithm for Real-Time Communications through Mixed WLAN Environments

    Science.gov (United States)

    Morioka, Yasufumi; Higashino, Takeshi; Tsukamoto, Katsutoshi; Komaki, Shozo

    Recent rapid development of high-speed wireless access technologies has created mixed WLAN (Wireless LAN) environments where QoS capable APs coexist with legacy APs. To provide QoS guarantee in this mixed WLAN environment, this paper proposes a new AP selection algorithm. The proposed algorithm assigns an STA (Station) to an AP in the overall WLAN service area. Simulation results show improvement in the VoIP performance in terms of an eMOS (estimated Mean Opinion Score) value and the FTP throughput compared to conventional algorithms.

  17. K-AP: Generating specified K clusters by efficient Affinity Propagation

    KAUST Repository

    Zhang, Xiangliang

    2010-12-01

    The Affinity Propagation (AP) clustering algorithm proposed by Frey and Dueck (2007) provides an understandable, nearly optimal summary of a data set. However, it suffers two major shortcomings: i) the number of clusters is vague with the user-defined parameter called self-confidence, and ii) the quadratic computational complexity. When aiming at a given number of clusters due to prior knowledge, AP has to be launched many times until an appropriate setting of self-confidence is found. The re-launched AP increases the computational cost by one order of magnitude. In this paper, we propose an algorithm, called K-AP, to exploit the immediate results of K clusters by introducing a constraint in the process of message passing. Through theoretical analysis and experimental validation, K-AP was shown to be able to directly generate K clusters as user defined, with a negligible increase of computational cost compared to AP. In the meanwhile, K-AP preserves the clustering quality as AP in terms of the distortion. K-AP is more effective than k-medoids w.r.t. the distortion minimization and higher clustering purity. © 2010 IEEE.

  18. Research reactors in Argentina

    International Nuclear Information System (INIS)

    Argentine Nuclear Development started in early fifties. In 1957, it was decided to built the first a research reactor. RA-1 reactor (120 kw, today licensed to work at 40 kW) started operation in January 1958. Originally RA-1 was an Argonaut (American design) reactor. In early sixties, the RA-1 core was changed. Fuel rods (20% enrichment) was introduced instead the old Argonaut core design. For that reason, a critical facility named RA-0 was built. After that, the RA-3 project started, to build a multipurpose 5 MW nuclear reactor MTR pool type, to produce radioisotopes and research. For that reason and to define the characteristics of the RA-3 core, another critical facility was built, RA-2. Initially RA-3 was a 90 % enriched fuel reactor, and started operation in 1967. When Atucha I NPP project started, a German design Power Reactor, a small homogeneous reactor was donated by the German Government to Argentina (1969). This was RA-4 reactor (20% enrichment, 1W). In 1982, RA-6 pool reactor achieved criticality. This is a 500 kW reactor with 90% enriched MTR fuel elements. In 1990, RA-3 started to operate fueled by 20% enriched fuel. In 1997, the RA-8 (multipurpose critical facility located at Pilcaniyeu) started to operate. RA-3 reactor is the most important CNEA reactor for Argentine Research Reactors development. It is the first in a succession of Argentine MTR reactors built by CNEA (and INVAP SE ) in Argentina and other countries: RA-6 (500 kW, Bariloche-Argentina), RP-10 (10MW, Peru), NUR (500 kW, Algeria), MPR (22 MW, Egypt). The experience of Argentinian industry permits to compete with foreign developed countries as supplier of research reactors. Today, CNEA has six research reactors whose activities have a range from education and promotion of nuclear activity, to radioisotope production. For more than forty years, Argentine Research Reactors are working. The experience of Argentine is important, and argentine firms are able to compete in the design and

  19. Westinghouse AP1000 internals heating rate distribution calculation using a 3D deterministic transport method

    International Nuclear Information System (INIS)

    Cost reduction and reliability increase are systematically pursued systems and components; this requires, amongst other, the availability of sophisticated computer programs and detailed analysis models. As an example, the core shroud, the structure having the function to maintain the core centered on its axis, is being designed in the Westinghouse AP1000, differently from previous plants, as a highly heterogeneous structure. Its thermal-mechanical sizing must take into due account accurately determined internal heat generation rates. The latter, if determined by combining 2D and 1D neutron and γ-ray calculations which imply the separation of spatial variables and are mainly applicable for fluxes in the reactor beltline region, may include overly conservative margins. On the other hand, Monte Carlo methods do not allow an easy quantification of the uncertainties related to overall calculation. Three-dimensional deterministic models, based on the discrete ordinate transport theory, have the potential to provide accurate design data; they can be also effective provided that the well-known difficulty to create and tune a complex geometrical model in a reasonable time is overcome and adequate computer resources are available to perform the calculation (until few years ago [Botta et al., 1996. Three-Dimensional Reactor Pressure Vessel Fast Neutron Fluence Calculations for the AP600 Using TORT, 3-D Deterministic Radiation Transport Computer Programs: Features, Applications and Perspectives, NEA/NSC/DOC, OECD/NEA. Paris, France], massive parallel computers (i.e. Cray Computers) available only to large national laboratories and selected industries had to be used). ANSALDO is acting as Westinghouse subcontractor and it supported Westinghouse in all AP1000 Licensing Process to NRC from 1999 to nowdays for the internal heating rate generation rate and RPV fluence calculations. As computer power growths up ANSALDO refined its calculation methodology in order to improve the

  20. Thai research reactor

    International Nuclear Information System (INIS)

    The Office of Atomic Energy for Peace (OAEP) was established in 1962, as a reactor center, by the virtue of the Atomic Energy for Peace Act, under operational policy and authority of the Thai Atomic Energy for Peace Commission (TAEPC); and under administration of Ministry of Science, Technology and Energy. It owns and operates the only Thai Research Reactor (TRR-1/M1). The TRR-1/M1 is a mixed reactor system constituting of the old MTR type swimming pool, irradiation facilities and cooling system; and TRIGA Mark III core and control instrumentation. The general performance of TRR-1/M1 is summarized in Table I. The safe operation of TRR-1/M1 is regulated by Reactor Safety Committee (RSC), established under TAEPC, and Health Physics Group of OAEP. The RCS has responsibility and duty to review of and make recommendations on Reactor Standing Orders, Reactor Operation Procedures, Reactor Core Loading and Requests for Reactor Experiments. In addition,there also exist of Emergency Procedures which is administered by OAEP. The Reactor Operation Procedures constitute of reactor operating procedures, system operating procedures and reactor maintenance procedures. At the level of reactor routine operating procedures, there is a set of Specifications on Safety and Operation Limits and Code of Practice from which reactor shift supervisor and operators must follow in order to assure the safe operation of TRR-1/M1. Table II is the summary of such specifications. The OAEP is now upgrading certain major components of the TRR-1/M1 such as the cooling system, the ventilation system and monitoring equipment to ensure their adequately safe and reliable performance under normal and emergency conditions. Furthermore, the International Atomic Energy Agency has been providing assistance in areas of operation and maintenance and safety analysis. (author)

  1. Nuclear Reactor Physics

    Science.gov (United States)

    Stacey, Weston M.

    2001-02-01

    An authoritative textbook and up-to-date professional's guide to basic and advanced principles and practices Nuclear reactors now account for a significant portion of the electrical power generated worldwide. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. Nuclear reactor physics is the core discipline of nuclear engineering, and as the first comprehensive textbook and reference on basic and advanced nuclear reactor physics to appear in a quarter century, this book fills a large gap in the professional literature. Nuclear Reactor Physics is a textbook for students new to the subject, for others who need a basic understanding of how nuclear reactors work, as well as for those who are, or wish to become, specialists in nuclear reactor physics and reactor physics computations. It is also a valuable resource for engineers responsible for the operation of nuclear reactors. Dr. Weston Stacey begins with clear presentations of the basic physical principles, nuclear data, and computational methodology needed to understand both the static and dynamic behaviors of nuclear reactors. This is followed by in-depth discussions of advanced concepts, including extensive treatment of neutron transport computational methods. As an aid to comprehension and quick mastery of computational skills, he provides numerous examples illustrating step-by-step procedures for performing the calculations described and chapter-end problems. Nuclear Reactor Physics is a useful textbook and working reference. It is an excellent self-teaching guide for research scientists, engineers, and technicians involved in industrial, research, and military applications of nuclear reactors, as well as government regulators who wish to increase their understanding of nuclear reactors.

  2. From the dual function lead AP2238 to AP2469, a multi-target-directed ligand for the treatment of Alzheimer's disease

    OpenAIRE

    Tarozzi, Andrea; Bartolini, Manuela; Piazzi, Lorna; Valgimigli, Luca; Amorati, Riccardo; Bolondi, Cecilia; Djemil, Alice; Mancini, Francesca; Andrisano, Vincenza; Rampa, Angela

    2014-01-01

    The development of drugs with different pharmacological properties appears to be an innovative therapeutic approach for Alzheimer's disease. In this article, we describe a simple structural modification of AP2238, a first dual function lead, in particular the introduction of the catechol moiety performed in order to search for multi-target ligands. The new compound AP2469 retains anti-acetylcholinesterase (AChE) and beta-site amyloid precursor protein cleaving enzyme (BACE)1 activities compar...

  3. Radioactive air emissions notice of construction for installation and operation of a waste retrieval system and tanks 241-AP-102 and 241-AP-104 project

    Energy Technology Data Exchange (ETDEWEB)

    DEXTER, M.L.

    1999-11-15

    This document serves as a notice of construction (NOC) pursuant to the requirements of Washington Administrative Code (WAC) 246 247-060, and as a request for approval to modify pursuant to 40 Code of Federal Regulations (CFR) 61 07 for the installation and operation of one waste retrieval system in the 24 1 AP-102 Tank and one waste retrieval system in the 241 AP 104 Tank Pursuant to 40 CFR 61 09 (a)( 1) this application is also intended to provide anticipated initial start up notification Its is requested that EPA approval of this application will also constitute EPA acceptance of the initial start up notification Project W 211 Initial Tank Retrieval Systems (ITRS) is scoped to install a waste retrieval system in the following double-shell tanks 241-AP 102-AP 104 AN 102, AN 103, AN-104, AN 105, AY 102 AZ 102 and SY-102 between now and the year 2011. Because of the extended installation schedules and unknowns about specific activities/designs at each tank, it was decided to submit NOCs as that information became available This NOC covers the installation and operation of a waste retrieval system in tanks 241 AP-102 and 241 AP 104 Generally this includes removal of existing equipment installation of new equipment and construction of new ancillary equipment and buildings Tanks 241 AP 102 and 241 AP 104 will provide waste feed for immobilization into a low activity waste (LAW) product (i.e. glass logs) The total effective dose equivalent (TEDE) to the offsite maximally exposed individual (MEI) from the construction activities is 0 045 millirem per year The unabated TEDE to the offsite ME1 from operation of the mixer pumps is 0 042 millirem per year.

  4. Radioactive air emissions notice of construction for installation and operation of a waste retrieval system and tanks 241-AP-102 and 241-AP-104 project

    International Nuclear Information System (INIS)

    This document serves as a notice of construction (NOC) pursuant to the requirements of Washington Administrative Code (WAC) 246 247-060, and as a request for approval to modify pursuant to 40 Code of Federal Regulations (CFR) 61 07 for the installation and operation of one waste retrieval system in the 24 1 AP-102 Tank and one waste retrieval system in the 241 AP 104 Tank Pursuant to 40 CFR 61 09 (a)( 1) this application is also intended to provide anticipated initial start up notification Its is requested that EPA approval of this application will also constitute EPA acceptance of the initial start up notification Project W 211 Initial Tank Retrieval Systems (ITRS) is scoped to install a waste retrieval system in the following double-shell tanks 241-AP 102-AP 104 AN 102, AN 103, AN-104, AN 105, AY 102 AZ 102 and SY-102 between now and the year 2011. Because of the extended installation schedules and unknowns about specific activities/designs at each tank, it was decided to submit NOCs as that information became available This NOC covers the installation and operation of a waste retrieval system in tanks 241 AP-102 and 241 AP 104 Generally this includes removal of existing equipment installation of new equipment and construction of new ancillary equipment and buildings Tanks 241 AP 102 and 241 AP 104 will provide waste feed for immobilization into a low activity waste (LAW) product (i.e. glass logs) The total effective dose equivalent (TEDE) to the offsite maximally exposed individual (MEI) from the construction activities is 0 045 millirem per year The unabated TEDE to the offsite ME1 from operation of the mixer pumps is 0 042 millirem per year

  5. Reactor containment and reactor safety in the United States

    International Nuclear Information System (INIS)

    The reactor safety systems of two reactors are studied aiming at the reactor containment integrity. The first is a BWR type reactor and is called Peachbottom 2, and the second is a PWR type reactor, and is called surry. (E.G.)

  6. SPES-2, AP600 intergral system test S01007 2 inch CL to core make-up tank pressure balance line break

    Energy Technology Data Exchange (ETDEWEB)

    Bacchiani, M.; Medich, C.; Rigamonti, M. [SIET S.p.A. Piacenza (Italy)] [and others

    1995-09-01

    The SPES-2 is a full height, full pressure experimental test facility reproducing the Westinghouse AP600 reactor with a scaling factor of 1/395. The experimental plant, designed and operated by SIET in Piacenza, consists of a full simulation of the AP600 primary core cooling system including all the passive and active safety systems. In 1992, Westinghouse, in cooperation with ENEL (Ente Nazionale per l` Energia Elettrica), ENEA (Enter per le numove Technlogie, l` Energia e l` Ambient), Siet (Societa Informazioni Esperienze Termoidraulich) and ANSALDO developed an experimental program to test the integrated behaviour of the AP600 passive safety systems. The SPES-2 test matrix, concluded in November 1994, has examined the AP600 passive safety system response for a range of small break LOCAs at different locations on the primary system and on the passive system lines; single steam generator tube ruptures with passive and active safety systems and a main steam line break transient to demonstrate the boration capability of passive safety systems for rapid cooldown. Each of the tests has provided detailed experimental results for verification of the capability of the analysis methods to predict the integrated passive safety system behaviour. Cold and hot shakedown tests have been performed on the facility to check the characteristics of the plant before starting the experimental campaign. The paper first presents a description of the SPES-2 test facility then the main results of S01007 test {open_quotes}2{close_quotes} Cold Leg (CL) to Core Make-up Tank (CMT) pressure balance line break{close_quotes} are reported and compared with predictions performed using RELAP5/mod3/80 obtained by ANSALDO through agreement with U.S.N.R.C. (U.S. Nuclear Regulatory Commission). The SPES-2 nodalization and all the calculations here presented were performed by ANSALDO and sponsored by ENEL as a part of pre-test predictions for SPES-2.

  7. TRIGA reactor main systems

    International Nuclear Information System (INIS)

    This module describes the main systems of low power (<2 MW) and higher power (≥2 MW) TRIGA reactors. The most significant difference between the two is that forced reactor cooling and an emergency core cooling system are generally required for the higher power TRIGA reactors. However, those TRIGA reactors that are designed to be operated above 3 MW also use a TRIGA fuel that is specifically designed for those higher power outputs (3 to 14 MW). Typical values are given for the respective systems although each TRIGA facility will have unique characteristics that may only be determined by the experienced facility operators. Due to the inherent wide scope of these research reactor facilities construction and missions, this training module covers those systems found at most operating TRIGA reactor facilities but may also discuss non-standard equipment that was found to be operationally useful although not necessarily required. (author)

  8. Evaluation of research reactors

    International Nuclear Information System (INIS)

    The present status of research reactors with highly enriched (93%) uranium fuel at JAERI, JRR-2 and JMTR is described. JRR-2 is a heterogeneous type of reactor, using heavy water as moderator and coolant. It uses both MTR type and cylindrical type of fuel elements. The maximum thermal power and the thermal neutron flux are 10 MW and 2x1014 n/cm2 see respectively. The reactor has been used for various experiments such as solid state physics, material irradiation, reactor fuel irradiation and radioisotope production. The JMTR is a multi-purpose tank type material testing reactor, and light water moderator and coolant, operated at 50 MW. The evaluation of lower enriched fuel and its consequences for both reactors is considered more especially

  9. Multipurpose research reactors

    International Nuclear Information System (INIS)

    The international symposium on the utilization of multipurpose research reactors and related international co-operation was organized by the IAEA to provide for information exchange on current uses of research reactors and international co-operative projects. The symposium was attended by about 140 participants from 36 countries and two international organizations. There were 49 oral presentations of papers and 24 poster presentations. The presentations were divided into 7 sessions devoted to the following topics: neutron beam research and applications of neutron scattering (6 papers and 1 poster), reactor engineering (6 papers and 5 posters), irradiation testing of fuel and material for fission and fusion reactors (6 papers and 10 posters), research reactor utilization programmes (13 papers and 4 posters), neutron capture therapy (4 papers), neutron activation analysis (3 papers and 4 posters), application of small reactors in research and training (11 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

  10. The nuclear soliton reactor

    International Nuclear Information System (INIS)

    The basic reactor physics of a completely novel nuclear fission reactor design - the soliton-reactor - is presented on the basis of a simple model. In such a reactor, the neutrons in the critical region convert either fertile material in the adjacent layers into fissile material or reduce the poisoning of fissile material in such a manner that successively new critical regions emerge. The result is an autocatalytically driven burn-up wave which propagates throughout the reactor. Thereby, the relevant characteristic spatial distributions (neutron flux, specific power density and the associated particle densities) are solitons - wave phenomena resulting from non-linear partial differential equations which do not change their shape during propagation. A qualitativley new kind of harnessing nuclear fission energy may become possible with fuel residence times comparable with the useful lifetime of the reactor system. In the long run, fast breeder systems which exploit the natural uranium and thorium resources, without any reprocessing capacity are imaginable. (orig.)

  11. Fast Spectrum Reactors

    CERN Document Server

    Todd, Donald; Tsvetkov, Pavel

    2012-01-01

    Fast Spectrum Reactors presents a detailed overview of world-wide technology contributing to the development of fast spectrum reactors. With a unique focus on the capabilities of fast spectrum reactors to address nuclear waste transmutation issues, in addition to the well-known capabilities of breeding new fuel, this volume describes how fast spectrum reactors contribute to the wide application of nuclear power systems to serve the global nuclear renaissance while minimizing nuclear proliferation concerns. Readers will find an introduction to the sustainable development of nuclear energy and the role of fast reactors, in addition to an economic analysis of nuclear reactors. A section devoted to neutronics offers the current trends in nuclear design, such as performance parameters and the optimization of advanced power systems. The latest findings on fuel management, partitioning and transmutation include the physics, efficiency and strategies of transmutation, homogeneous and heterogeneous recycling, in addit...

  12. TinyCoAP: A Novel Constrained Application Protocol (CoAP Implementation for Embedding RESTful Web Services in Wireless Sensor Networks Based on TinyOS

    Directory of Open Access Journals (Sweden)

    Anna Calveras

    2013-05-01

    Full Text Available In this paper we present the design and implementation of the Constrained Application Protocol (CoAP for TinyOS, which we refer to as TinyCoAP. CoAP seeks to apply the same application transfer paradigm and basic features of HTTP to constrained networks, while maintaining a simple design and low overhead. The design constraints of Wireless Sensor Networks (WSNs require special attention in the design process of the CoAP implementation. We argue that better performance and minimal resource consumption can be achieved developing a native library for the operating system embedded in the network. TinyOS already includes in its distribution an implementation of CoAP called CoapBlip. However, this is based on a library not originally designed to meet the requirements of TinyOS. We demonstrate the effectiveness of our approach by a comprehensive performance evaluation. In particular, we test and evaluate TinyCoAP and CoapBlip in a real scenario, as well as solutions based on HTTP. The evaluation is performed in terms of latency, memory occupation, and energy consumption. Furthermore, we evaluate the reliability of each solution by measuring the goodput obtained in a channel affected by Rayleigh fading. We also include a study on the effects that high workloads have on a server.

  13. Transient Fcho1/2⋅Eps15/R⋅AP-2 Nanoclusters Prime the AP-2 Clathrin Adaptor for Cargo Binding.

    Science.gov (United States)

    Ma, Li; Umasankar, Perunthottathu K; Wrobel, Antoni G; Lymar, Anastasia; McCoy, Airlie J; Holkar, Sachin S; Jha, Anupma; Pradhan-Sundd, Tirthadipa; Watkins, Simon C; Owen, David J; Traub, Linton M

    2016-06-01

    Clathrin-coated vesicles form by rapid assembly of discrete coat constituents into a cargo-sorting lattice. How the sequential phases of coat construction are choreographed is unclear, but transient protein-protein interactions mediated by short interaction motifs are pivotal. We show that arrayed Asp-Pro-Phe (DPF) motifs within the early-arriving endocytic pioneers Eps15/R are differentially decoded by other endocytic pioneers Fcho1/2 and AP-2. The structure of an Eps15/R⋅Fcho1 μ-homology domain complex reveals a spacing-dependent DPF triad, bound in a mechanistically distinct way from the mode of single DPF binding to AP-2. Using cells lacking FCHO1/2 and with Eps15 sequestered from the plasma membrane, we establish that without these two endocytic pioneers, AP-2 assemblies are fleeting and endocytosis stalls. Thus, distinct DPF-based codes within the unstructured Eps15/R C terminus direct the assembly of temporary Fcho1/2⋅Eps15/R⋅AP-2 ternary complexes to facilitate conformational activation of AP-2 by the Fcho1/2 interdomain linker to promote AP-2 cargo engagement. PMID:27237791

  14. United-States: green light for the construction of reactors; Etats-Unis: une premiere depuis 1986: feu vert a la construction de reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2012-01-15

    On 9. february 2012 the American Federal Authorities gave their green light for the construction of new nuclear reactors. The NRC has given its agreement for the commissioning of the reactors 3 and 4 of the Vogtle plant. These 2 reactors are AP1000 from Toshiba, they are already being constructed and they are expected to begin operations in 2016. They will be the first reactors to be commissioned in the Usa since the inauguration of the River Bend plant in 1986. (A.C.)

  15. Enhancing and Archiving the APS Catalog of the POSS I

    Science.gov (United States)

    Humphreys, Roberta M.

    2003-01-01

    We have worked on two different projects: 1) Archiving the APS Catalog of the POSS I for distribution to NASA's NED at IPAC, SIMBAD in France, and individual astronomers and 2) The automated morphological classification of galaxies. We have completed archiving the Catalog into easily readable binary files. The database together with the software to read it has been distributed on DVD's to the national and international data centers and to individual astronomers. The archived Catalog contains more than 89 million objects in 632 fields in the first epoch Palomar Observatory Sky Survey. Additional image parameters not available in the original on-line version are also included in the archived version. The archived Catalog is also available and can be queried at the APS web site (URL: http://aps.umn.edu) which has been improved with a much faster and more efficient querying system. The Catalog can be downloaded as binary datafiles with the source code for reading it. It is also being integrated into the SkyQuery system which includes the Sloan Digital Sky Survey, 2MASS, and the FIRST radio sky survey. We experimented with different classification algorithms to automate the morphological classification of galaxies. This is an especially difficult problem because there are not only a large number of attributes or parameters and measurement uncertainties, but also the added complication of human disagreement about the adopted types. To solve this problem we used 837 galaxy images from nine POSS I fields at the North Galactic Pole classified by two independent astronomers for which they agree on the morphological types. The initial goal was to separate the galaxies into the three broad classes relevant to issues of large scale structure and galaxy formation and evolution: early (ellipticals and lenticulars), spirals, and late (irregulars) with an accuracy or success rate that rivals the best astronomer classifiers. We also needed to identify a set of parameters derived

  16. Preface: 18th Aps-Sccm and 24th Airapt

    Science.gov (United States)

    Collins, Gilbert; Moore, David S.; Yoo, Choong-Shik; Buttler, William; Furlanetto, Michael; Evans, William

    2014-05-01

    The 18th Biennial International Conference of the APS Topical Group on Shock Compression of Condensed Matter in conjunction with the 24th Biennial International Conference of the International Association for the Advancement of High Pressure Science & Technology (AIRAPT) was held at the Westin Hotel in Seattle, Washington from 7-12 July, 2013. This is only the second time that these two organizations have held a Joint Conference — the first was 20 years previous (1993) in Colorado Springs, Colorado. Seattle was chosen for this joint conference because of its central location for the world-wide attendees as well as its metropolitan vibrancy. The scientific program consisted of 858 scheduled presentations organized into 23 topical areas and included contributed (537), invited (95), and plenary (6) lectures, as well as two poster sessions with 110 posters each. The scientific focus of the Joint Conference was on fundamental and applied research topics related to the static or dynamic compression of condensed matter. This multidisciplinary field of research encompasses areas of physics, chemistry, materials science, mechanics, geophysics and planetary physics, and applied mathematics. Experimental, computational and theoretical studies all play important roles. The organizers endeavored to intertwine static and dynamic experimental alongside computational and theoretical studies of similar materials in the organization of the sessions. This goal was aided by the addition of three special focus sessions on deep carbon budget, high energy density materials, and dynamic response of materials. 722 scientists and engineers from 25 countries registered at the conference, including 132 students from 12 countries. The attendee countries represented included: Argentina (2), Australia (2), Brazil (3), Canada (25), China (22), Czech Republic (2), France (35), Germany (19), India (6), Israel (21), Italy (10), Japan (49), Netherlands (1), Poland (1), Portugal (2), Russia (26

  17. Fusion reactor research

    International Nuclear Information System (INIS)

    This work covers four separate areas: (1) development of technology for processing liquid lithium from blankets, (2) investigation of hydrogen isotope permeation in candidate structural metals and alloys for near-term fusion reactors, (3) analytical studies encompassing fusion reactor thermal hydraulics, tritium facility design, and fusion reactor safety, and (4) studies involving dosimetry and damage analysis. Recent accomplishments in each of these areas are summarized

  18. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    The Integral Fast Reactor (IFR) is an innovative liquid metal reactor concept being developed at Argonne National Laboratory. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system. This paper describes the key features and potential advantages of the IFR concept, with emphasis on its safety characteristics. 3 refs., 4 figs., 1 tab

  19. The replacement research reactor

    International Nuclear Information System (INIS)

    As a consequences of the government decision in September 1997. ANSTO established a replacement research reactor project to manage the procurement of the replacement reactor through the necessary approval, tendering and contract management stages This paper provides an update of the status of the project including the completion of the Environmental Impact Statement. Prequalification and Public Works Committee processes. The aims of the project, management organisation, reactor type and expected capabilities are also described

  20. PFBR reactor protection

    International Nuclear Information System (INIS)

    Design philosophy adopted for Prototype Fast breeder Reactor (PFBR) is a classical one and has the following features: triplicated sensors for measuring important safety parameters; two independent reactor protection Logic Systems based on solid state devices; reactivity control achieved by control rods; gas equipped modules at the core blanket interface providing negative reactivity. Design verification of these features showed that safety of the reactor can be achieved by a traditional approach since the inherent features of LMFBR make this easy

  1. Reactor BR2

    International Nuclear Information System (INIS)

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported

  2. TRIGA reactor characteristics

    International Nuclear Information System (INIS)

    This module describes the general design, characteristics and parameters of TRIGA reactors and fuels. It is recommended that most of this information should be incorporated into any reactor operator training program and, in many cases, the facility Safety Analysis Report. It is oriented to teach the basics of the physics and mechanical design of the TRIGA fuel as well as its unique operational characteristics and the differences between TRIGA fuels and others more traditional reactor fuels. (nevyjel)

  3. Reactor Safety Analysis

    International Nuclear Information System (INIS)

    The objective of SCK-CEN's programme on reactor safety is to develop expertise in probabilistic and deterministic reactor safety analysis. The research programme consists of four main activities, in particular the development of software for reliability analysis of large systems and participation in the international PHEBUS-FP programme for severe accidents, the development of an expert system for the aid to diagnosis; the development and application of a probabilistic reactor dynamics method. Main achievements in 1999 are reported

  4. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    Research and development activities in the Department of Reactor Engineering in fiscal 1984 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, reactor physics experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, safeguards technology, and activities of the Committee on Reactor Physics. (author)

  5. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research and development activities in the Division of Reactor Engineering in fiscal 1981 are described. The work of the Division is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committee on Reactor Physics. (author)

  6. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research activities in the Division of Reactor Engineering in fiscal 1979 are described. The work of the Division is closely related to development of multi-purpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committees on Reactor Physics and on Decomissioning of Nuclear Facilities. (author)

  7. New reactor concepts

    International Nuclear Information System (INIS)

    The document gives a summary of new nuclear reactor concepts from a technological point of view. Belgium supports the development of the European Pressurized-Water Reactor, which is an evolutionary concept based on the European experience in Pressurized-Water Reactors. A reorientation of the Belgian choice for this evolutionary concept may be required in case that a decision is taken to burn plutonium, when the need for flexible nuclear power plants arises or when new reactor concepts can demonstrate proved benefits in terms of safety and cost

  8. Reactor construction steels

    International Nuclear Information System (INIS)

    The basic functions of light water reactor components are shown on the example of a pressurized water reactor and the requirements resulting therefrom for steel, the basic structural material, are derived. A detailed analysis of three main groups of reactor steels is presented and the applications are indicated of low-alloyed steels, high-alloyed austenitic steels, and steels with a high content of Ni and of alloying additions for steam generator pipes. An outline is given of prospective fast breeder reactor steels. (J.K.)

  9. Commercialization of fast reactors

    International Nuclear Information System (INIS)

    Comparative analysis has been performed of capital and fuel cycle costs for fast BN-type and pressurized light water VVER-type reactors. As a result of materials demand and components costs comparison of NPPs with VVER-1000 and BN-600 reactors, respectively, conclusion was made, that under equal conditions of the comparison, NPP with fast reactor had surpassed the specific capital cost of NPP with VVER by about 30 - 40 %. Ways were determined for further decrease of this difference, as well as for the fuel cycle cost reduction, because at present it is higher than that of VVER-type reactors. (author)

  10. Mirror fusion reactors

    International Nuclear Information System (INIS)

    Conceptual design studies were made of fusion reactors based on the three current mirror-confinement concepts: the standard mirror, the tandem mirror, and the field-reversed mirror. Recent studies of the standard mirror have emphasized its potential as a fusion-fission hybrid reactor, designed to produce fuel for fission reactors. We have designed a large commercial hybrid and a small pilot-plant hybrid based on standard mirror confinement. Tandem mirror designs include a commercial 1000-MWe fusion power plant and a nearer term tandem mirror hybrid. Field-reversed mirror designs include a multicell commercial reactor producing 75 MWe and a single-cell pilot plant

  11. Natural convection type reactor

    International Nuclear Information System (INIS)

    In a natural convection type nuclear reactor, a reactor core is disposed such that the top of the reactor core is always situated in a flooded position even if pipelines connected to the pressure vessel are ruptured and the level at the inside of the reactor vessel is reduced due to flashing. Further, a lower dry well situated below the pressure vessel is disposed such that it is in communication with a through hole to a pressure suppression chamber situated therearound and the reactor core is situated at the level lower than that of the through hole. If pipelines connected to the pressure vessel are ruptured to cause loss of water, although the water level is lowered after the end of the flashing, the reactor core is always flooded till the operation of a pressure accummulation water injection system to prevent the top of the reactor core even from temporary exposure. Further, injected water is discharged to the outside of the pressure vessel, transferred to the lower dry well, and flows through the through hole to the pressure control chamber and cools the surface of the reactor pressure vessel from the outside. Accordingly, the reactor core is cooled to surely and efficiently remove the after-heat. (N.H.)

  12. INVAP's Research Reactor Designs

    International Nuclear Information System (INIS)

    INVAP, an Argentine company founded more than three decades ago, is today recognized as one of the leaders within the research reactor industry. INVAP has participated in several projects covering a wide range of facilities, designed in accordance with the requirements of our different clients. For complying with these requirements, INVAP developed special skills and capabilities to deal with different fuel assemblies, different core cooling systems, and different reactor layouts. This paper summarizes the general features and utilization of several INVAP research reactor designs, from subcritical and critical assemblies to high-power reactors IAEA safety

  13. Reactor power control device

    International Nuclear Information System (INIS)

    The present invention provides a control device which can conduct scram and avoid lowering of the power of a nuclear power plant upon occurrence of earthquakes. Namely, the device of the present invention comprises, in addition to an existent power control device, (1) an earthquake detector for detecting occurrence and annihilation of earthquakes and (2) a reactor control device for outputting control rod operation signals and reactor core flow rate control signals depending on the earthquake detection signals from the detector, and reactor and plant information. With such a constitution, although the reactor is vibrated by earthquakes, the detector detects slight oscillations of the reactor by initial fine vibration waves as premonitory symptoms of serious earthquakes. The earthquake occurrence signals are outputted to the reactor control device. The reactor control device, receiving the signals, changes the position of control rods by way of control rod driving mechanisms to make the axial power distribution in the reactor core to a top peak type. As a result, even if the void amount in the reactor core is reduced by the subsequent actual earthquakes, since the void amount is moved, effects on the increase of neutron fluxes by the actual earthquakes is small. (I.S.)

  14. Nuclear reactor internals arrangement

    International Nuclear Information System (INIS)

    A nuclear reactor internals arrangement is disclosed which facilitates reactor refueling. A reactor vessel and a nuclear core is utilized in conjunction with an upper core support arrangement having means for storing withdrawn control rods therein. The upper core support is mounted to the underside of the reactor vessel closure head so that upon withdrawal of the control rods into the upper core support, the closure head, the upper core support and the control rods are removed as a single unit thereby directly exposing the core for purposes of refueling

  15. Fusion Reactor Materials

    International Nuclear Information System (INIS)

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

  16. Understanding and Using the New Guided-Inquiry AP Chemistry Laboratory Manual

    Science.gov (United States)

    Cacciatore, Kristen L.

    2014-01-01

    To support teaching and learning in the advanced placement (AP) chemistry laboratory, the College Board published a laboratory manual, "AP Chemistry Guided-Inquiry Experiments: Applying the Science Practices," in 2013 as part of the redesigned course. This article provides a discussion of the rationale for the existence of the manual as…

  17. History of the APS Topical Group on Shock Compression of Condensed Matter

    Energy Technology Data Exchange (ETDEWEB)

    Forbes, J W

    2001-10-19

    In order to provide broader scientific recognition and to advance the science of shock compressed condensed matter, a group of American Physical Society (APS) members worked within the Society to make this field an active part of the APS. Individual papers were presented at APS meetings starting in the 1940's and shock wave sessions were organized starting with the 1967 Pasadena meeting. Shock wave topical conferences began in 1979 in Pullman, WA. Signatures were obtained on a petition in 1984 from a balanced cross-section of the shock wave community to form an APS Topical Group (TG). The APS Council officially accepted the formation of the Shock Compression of Condensed Matter (SCCM) TG at its October 1984 meeting. This action firmly aligned the shock wave field with a major physical science organization. Most early topical conferences were sanctioned by the APS while those held after 1992 were official APS meetings. The topical group organizes a shock wave topical conference in odd numbered years while participating in shock wavehigh pressure sessions at APS general meetings in even numbered years.

  18. The History of the APS Shock Compression of Condensed Matter Topical Group

    Energy Technology Data Exchange (ETDEWEB)

    Forbes, J W

    2001-05-02

    In order to provide broader scientific recognition and to advance the science of shock compressed condensed matter, a group of American Physical Society (APS) members worked within the Society to make this field an active part of the APS. Individual papers were presented at APS meetings starting in the 1940's and shock wave sessions were organized starting with the 1967 Pasadena meeting. Shock wave topical conferences began in 1979 in Pullman, WA. Signatures were obtained on a petition in 1984 from a balanced cross-section of the shock wave community to form an APS Topical Group (TG). The APS Council officially accepted the formation of the Shock Compression of Condensed Matter (SCCM) TG at its October 1984 meeting. This action firmly aligned the shock wave field with a major physical science organization. Most early topical conferences were sanctioned by the APS while those held after 1992 were official APS meetings. The topical group organizes a shock wave topical conference in odd numbered years while participating in shock wave/high pressure sessions at APS general meetings in even numbered years.

  19. NACS: non-overlapping AP's caching scheme to reduce handoff in 802.11 wireless LAN

    CERN Document Server

    Tariq, Usman; Hong, Man-Pyo

    2011-01-01

    With the escalation of the IEEE 802.11 based wireless networks, voice over IP and analogous applications are also used over wireless networks. Recently, the wireless LAN systems are spaciously deployed for public Internet services. In public wireless LAN systems, reliable user authentication and mobility support are indispensable issues. When a mobile device budges out the range of one access point (AP) and endeavor to connect to new AP, it performs handoff. Contemporarily, PNC and SNC were proposed to propagate the MN context to the entire neighboring AP's on the wireless network with the help of neighbor graph. In this paper, we proposed a non-overlapping AP's caching scheme (NACS), which propagates the mobile node context to those AP's which do not overlap with the current AP. To capture the topology of non-overlapping AP's in the wireless network, non-overlapping graph (NOG) is generated at each AP. Simulation results shows that NACS reduces the signaling cost of propagating the MN context to the neighbor...

  20. The Freshman Nine: Helping High School Freshmen Be Successful in AP Human Geography

    Science.gov (United States)

    Garner, Jennifer

    2012-01-01

    Teaching AP Human Geography to freshmen seems like a daunting task and while there are many arguments both for and against offering the course to freshmen, for many teachers it is reality. In this article, the author offers nine tips to help high school freshmen be successful in the course and on the AP exam.