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Sample records for experiment p4 lmfbr

  1. Applications of simulation experiments in LMFBR core materials technology

    International Nuclear Information System (INIS)

    Appleby, W.K.

    1976-01-01

    The development of charged particle bombardment experiments to simulate neutron irradiation induced swelling in austenitic alloys is briefly described. The applications of these techniques in LMFBR core materials technology are discussed. It is shown that use of the techniques to study the behavior of cold-worked Type-316 was instrumental in demonstrating at an early date the need for advanced materials. The simulation techniques then were used to identify alloying elements which can markedly decrease swelling and thus a focused reactor irradiation program is now in place to allow the future use of a lower swelling alloy for LMFBR core components

  2. LMFBR operational safety: the EBR-II experience

    International Nuclear Information System (INIS)

    Sackett, J.I.; Allen, N.L.; Dean, E.M.; Fryer, R.M.; Larson, H.A.; Lehto, W.K.

    1978-01-01

    The mission of the Experimental Breeder Reactor II (EBR-II) has evolved from that of a small LMFBR demonstration plant to a major irradiation-test facility. Because of that evolution, many operational-safety issues have been encountered. The paper describes the EBR-II operational-safety experience in four areas: protection-system design, safety-document preparation, tests of off-normal reactor conditions, and tests of elements with breached cladding

  3. LMFBR safety testing needs and the conceptual design of a new safety research experiment facility

    International Nuclear Information System (INIS)

    Marchaterre, J.F.; Matlock, R.G.; Goldman, A.J.

    1975-09-01

    Experiment needs for the LMFBR safety program are reviewed. The screening of reactor concepts which would meet the needs is described and a conceptual design for a new safety research experiment facility is presented

  4. LMFBR source term experiments with rupture disk discharge under sodium

    International Nuclear Information System (INIS)

    Minges, J.; Schuetz, W.

    1993-05-01

    In the frame of the KfK research program FAUST, contributions are given to the assessment of the instantaneous source term in case of an LMFBR loss-of-flow accident with expanding fuel or sodium vapour. The main goal of the program is to achieve information, mainly by experiments, on the retention capability of the primary sodium pool for fuel and fission products. For that purpose, it is necessary to investigate the interaction of bubble and aerosol behaviour after a pressure discharge, and the subsequent aerosol transport. After a series of water tests (FAUST-1), rupture disk discharge tests under 500 C sodium up to 3.81 MPa were performed during the phase FAUST-2 with the two test facilities 2A (about 2 liters of sodium) and 2B (about 200 liters of sodium). The discharge tests were performed with pressurized argon gas and admixtures of the simulation materials Cs, Csl, Nal, l 2 , SrO, and UO 2 . Cs was a liquid, l 2 vapour, and all other substances solid particles. Besides UO 2 , non-radioactive material was used (natural isotopes). The retention capability of liquid sodium is expressed by retention factors RF. In general, RF is defined as the mass ratio of discharged amount, and the amount which is detected in the cover gas for the relevant species. From sampling immediately after the discharge, the instantaneous retention factors are deduced. From retarded sampling, the 'delayed factors' follow. High pressure discharge creates two important removal mechanisms, namely 'impaction by inertia relative to the bubble oscillations' and 'wash-out by sedimentation of entrained sodium droplets'. On the other hand, the retention of particles enclosed in a buoyantly rising bubble is significantly smaller. (orig.) [de

  5. Operational-safety advantages of LMFBR's: the EBR-II experience and testing program

    International Nuclear Information System (INIS)

    Sackett, J.I.; Lindsay, R.W.; Golden, G.H.

    1982-01-01

    LMFBR's contain many inherent characteristics that simplify control and improve operating safety and reliability. The EBR-II design is such that good advantage was taken of these characteristics, resulting in a vary favorable operating history and allowing for a program of off-normal testing to further demonstrate the safe response of LMFBR's to upsets. The experience already gained, and that expected from the future testing program, will contribute to further development of design and safety criteria for LMFBR's. Inherently safe characteristics are emphasized and include natural convective flow for decay heat removal, minimal need for emergency power and a large negative reactivity feedback coefficient. These characteristics at EBR-II allow for ready application of computer diagnosis and control to demonstrate their effectiveness in response to simulated plant accidents. This latter testing objective is an important part in improvements in the man-machine interface

  6. Benchmark physics experiment of metallic-fueled LMFBR at FCA. 2

    International Nuclear Information System (INIS)

    Iijima, Susumu; Oigawa, Hiroyuki; Ohno, Akio; Sakurai, Takeshi; Nemoto, Tatsuo; Osugi, Toshitaka; Satoh, Kunio; Hayasaka, Katsuhisa; Bando, Masaru.

    1993-10-01

    An availability of data and method for a design of metallic-fueled LMFBR is examined by using the experiment results of FCA assembly XVI-1. Experiment included criticality and reactivity coefficients such as Doppler, sodium void, fuel shifting and fuel expansion. Reaction rate ratios, sample worth and control rod worth were also measured. Analysis was made by using three-dimensional diffusion calculations and JENDL-2 cross sections. Predictions of assembly XVI-1 reactor physics parameters agree reasonably well with the measured values, but for some reactivity coefficients such as Doppler, large zone sodium void and fuel shifting further improvement of calculation method was need. (author)

  7. Operational-safety advantages of LMFBR's: the EBR-II experience and testing program

    Energy Technology Data Exchange (ETDEWEB)

    Sackett, J.I.; Lindsay, R.W.; Golden, G.H.

    1982-01-01

    LMFBR's contain many inherent characteristics that simplify control and improve operating safety and reliability. The EBR-II design is such that good advantage was taken of these characteristics, resulting in a vary favorable operating history and allowing for a program of off-normal testing to further demonstrate the safe response of LMFBR's to upsets. The experience already gained, and that expected from the future testing program, will contribute to further development of design and safety criteria for LMFBR's. Inherently safe characteristics are emphasized and include natural convective flow for decay heat removal, minimal need for emergency power and a large negative reactivity feedback coefficient. These characteristics at EBR-II allow for ready application of computer diagnosis and control to demonstrate their effectiveness in response to simulated plant accidents. This latter testing objective is an important part in improvements in the man-machine interface. (MMI)

  8. Simulation of sodium boiling experiments with THERMIT sodium version. [LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Huh, K.Y.

    1982-05-01

    Natural and forced convection experiments (SBTF and French) are simulated with the sodium version of the thermal-hydraulic computer code THERMIT. Simulation is done for the test section with the pressure-velocity boundary condition and subsequently extended to the whole loop. For the test section simulation, a steady-state and transient calculations are performed and compared with experimental data. For the loop simulation, two methods are used, a simulated 1-D loop and an actual 1-D loop. In the simulated 1-D loop analysis, the vapor density is increased by one hundred and two hundred times to avoid the code failure and the results still showed some of the important characteristics of the two-phase flow oscillation in a loop. A mathematical model is suggested for the two-phase flow oscillation. In the actual 1-D loop, only the single phase calculation was performed and turned out to be nearly the same as the simulated 1-D loop single phase results.

  9. LMFBR source term experiments in the Fuel Aerosol Simulant Test (FAST) facility

    Energy Technology Data Exchange (ETDEWEB)

    Petrykowski, J.C.; Longest, A.W.

    1985-01-01

    The transport of uranium dioxide (UO/sub 2/) aerosol through liquid sodium was studied in a series of ten experiments in the Fuel Aerosol Simulant Test (FAST) facility at Oak Ridge National Laboratory (ORNL). The experiments were designed to provide a mechanistic basis for evaluating the radiological source term associated with a postulated, energetic core disruptive accident (CDA) in a liquid metal fast breeder reactor (LMFBR). Aerosol was generated by capacitor discharge vaporization of UO/sub 2/ pellets which were submerged in a sodium pool under an argon cover gas. Measurements of the pool and cover gas pressures were used to study the transport of aerosol contained by vapor bubbles within the pool. Samples of cover gas were filtered to determine the quantity of aerosol released from the pool. The depth at which the aerosol was generated was found to be the most critical parameter affecting release. The largest release was observed in the baseline experiment where the sample was vaporized above the sodium pool. In the nine ''undersodium'' experiments aerosol was generated beneath the surface of the pool at depths varying from 30 to 1060 mm. The mass of aerosol released from the pool was found to be a very small fraction of the original specimen. It appears that the bulk of aerosol was contained by bubbles which collapsed within the pool. 18 refs., 11 figs., 4 tabs.

  10. LMFBR operational safety

    International Nuclear Information System (INIS)

    Sackett, J.I.; Allen, N.L.; Dean, E.M.; Fryer, R.M.; Larson, H.A.; Lehto, W.K.

    1978-01-01

    The mission of the Experimental Breeder Reactor II (EBR-II) has envolved from that of a small LMFBR demonstration plant to a major irradiation-test facility. Because of that evolution, many operational-safety issues have been encountered. This paper describes the EBR-II operational-safety experience in four areas: protection-system design, safety-document preparation, tests of off-normal reactor conditions, and tests of elements with breached cladding. (author)

  11. SLSF in-reactor local fault safety experiment P4. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Thompson, D. H.; Holland, J. W.; Braid, T. H.; Ragland, W. A.

    1985-09-01

    The Sodium Loop Safety Facility (SLSF), a major facility in the US fast-reactor safety program, has been used to simulate a variety of sodium-cooled fast reactor accidents. SLSF experiment P4 was conducted to investigate the behavior of a "worse-than-case" local fault configuration. Objectives of this experiment were to eject molten fuel into a 37-pin bundle of full-length Fast-Test-Reactor-type fuel pins form heat-generating fuel canisters, to characterize the severity of any molten fuel-coolant interaction, and to demonstrate that any resulting blockage could either be tolerated during continued power operation or detected by global monitors to prevent fuel failure propagation. The design goal for molten fuel release was 10 to 30 g. Explusion of molten fuel from fuel canisters caused failure of adjacent pins and a partial flow channel blockage in the fuel bundle during full-power operation. Molten fuel and fuel debris also lodged against the inner surface of the test subassembly hex-can wall. The total fuel disruption of 310 g evaluated from posttest examination data was in excellent agreement with results from the SLSF delayed neutron detection system, but exceeded the target molten fuel release by an order of magnitude. This report contains a summary description of the SLSF in-reactor loop and support systems and the experiment operations. results of the detailed macro- and microexamination of disrupted fuel and metal and results from the analysis of the on-line experimental data are described, as are the interpretations and conclusions drawn from the posttest evaluations. 60 refs., 74 figs.

  12. Strategies in development of advanced fuels for LMFBR

    International Nuclear Information System (INIS)

    Handa, Muneo

    1976-12-01

    Overseas strategies in development of advanced fuels for LMFBR are reviewed. Recent irradiation experiment and out-of-pile test data of the fuels are given in detail. The present status of development of oxide fueled LMFBR is also treated. (auth.)

  13. The P4 Parallel Programming System, the Linda Environment, and Some Experiences with Parallel Computation

    Directory of Open Access Journals (Sweden)

    Allan R. Larrabee

    1993-01-01

    Full Text Available The first digital computers consisted of a single processor acting on a single stream of data. In this so-called "von Neumann" architecture, computation speed is limited mainly by the time required to transfer data between the processor and memory. This limiting factor has been referred to as the "von Neumann bottleneck". The concern that the miniaturization of silicon-based integrated circuits will soon reach theoretical limits of size and gate times has led to increased interest in parallel architectures and also spurred research into alternatives to silicon-based implementations of processors. Meanwhile, sequential processors continue to be produced that have increased clock rates and an increase in memory locally available to a processor, and an increase in the rate at which data can be transferred to and from memories, networks, and remote storage. The efficiency of compilers and operating systems is also improving over time. Although such characteristics limit maximum performance, a large improvement in the speed of scientific computations can often be achieved by utilizing more efficient algorithms, particularly those that support parallel computation. This work discusses experiences with two tools for large grain (or "macro task" parallelism.

  14. Fuel-disruption experiments under high-ramp-rate heating conditions. [LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Wright, S.A.; Worledge, D.H.; Cano, G.L.; Mast, P.K.; Briscoe, F.

    1983-10-01

    This topical report presents the preliminary results and analysis of the High Ramp Rate fuel-disruption experiment series. These experiments were performed in the Annular Core Research Reactor at Sandia National Laboratories to investigate the timing and mode of fuel disruption during the prompt-burst phase of a loss-of-flow accident. High-speed cinematography was used to observe the timing and mode of the fuel disruption in a stack of five fuel pellets. Of the four experiments discussed, one used fresh mixed-oxide fuel, and three used irradiated mixed-oxide fuel. Analysis of the experiments indicates that in all cases, the observed disruption occurred well before fuel-vapor pressure was high enough to cause the disruption. The disruption appeared as a rapid spray-like expansion and occurred near the onset of fuel melting in the irradiated-fuel experiments and near the time of complete fuel melting in the fresh-fuel experiment. This early occurrence of fuel disruption is significant because it can potentially lower the work-energy release resulting from a prompt-burst disassembly accident.

  15. Analysis of LMFBR explosion model experiments by means of the SURBOUM-II code

    International Nuclear Information System (INIS)

    Stievenart, M.; Bouffioux, P.; Egleme, M.; Fabry, J.P.; Lamotte, H.

    1975-01-01

    Experiments have been carried out to simulate in small scale vessels the occurrence of an Hypothetical Core Disruptive Accident (HCDA) for the SNR-300 reactor. In parallel with the experimental programme, the (2D) computer code SURBOUM-II has been developed. The code computes the two-dimensional fluid flow within the system in case of a core explosion. The fluid is assumed incompressible and the deformations of the concrete shell(s) and vessel(s) are calculated by means of the thin shell theory. Perforated dip plates which are included in the model are treated as a particular type of boundary conditions involving empirical pressure drop versus flow relationships. The first part of the interpretation work was the determination of the pressure-volume relationship of the slow burning charge used to simulate the HCDA. This has been achieved by an original trial and error method built in the code which fits best the experimental impulse time records obtained in bare charge experiments fired in overstrong vessels. Other experiments carried out in overstrong vessels and involving perforated dip plate above the core to damp out the fluid impact on the roof were calculated and the comparison of the theoretical and experimental impulse time curves was satisfactory. Further experiments, including or not the perforated dip plate, carried out in yielding vessels were also interpreted. For those experiments the scope of the work was the comparison of calculated and measured deformation of the vessel. The agreement obtained is satisfactory, through the code seems to overestimate slightly the final deformation. (Auth.)

  16. Analysis of LMFBR explosion model experiments by means of the SURBOUM-II code

    International Nuclear Information System (INIS)

    Stievenart, M.; Bouffioux, P.; Egleme, M.; Fabry, J.P.; Lamotte, H.

    1975-01-01

    During the last four years experiments were carried out at JRC-Ispra in the frame of a collaboration contract between BELGONUCLEAIRE and EURATOM to stimulate in small scale vessels the occurrence of an Hypothetical Core Disruptive Accident (hcda) of the SNR-300 reactor. The 2D computer code SURBOUM-II has been developed in parallel with the experimental programme. That code computes the two-dimensional fluid flow within the system in case of a core explosion. The fluid is assumed uncompressible and the deformations of the concentric shell(s) and vessel(s) are calculated by means of the thin shell theory. Perforated dip plates which are included in the model are treated as a particular type of boundary conditions involving empirical pressure drop versus flow relationships. The first part of the interpretation work was the determination of the pressure-volume relationship of the slow burning charge used to stimulate the hcda. This has been achieved by an original trial and error method built in the code which fits bets the experimental impulse time records obtained in bare charge experiments fired in overstrong vessels. Other experiments carried out in overstrong vessels and involving perforated dip plate above the core to damp out the fluid impact on the roof were calculated and the comparison of the theoretical and experimental impulse time curves was satisfactory. Further experiments, including or not the perforated dip plate, carried out in yielding vessels were also interpreted. For those experiments the scope of the work was the comparison of calculated and measured deformation of the vessel. The agreement obtained is satisfactory, though the code seems to overestimate slightly the final deformation

  17. Transmission experiment by the simulated LMFBR model and propagation analysis of acoustic signals

    International Nuclear Information System (INIS)

    Kobayashi, Kenji; Yasuda, Tsutomu; Araki, Hitoshi.

    1981-01-01

    Acoustic transducers to detect a boiling of sodium may be installed in the upper structure and at the upper position of reactor vessel wall under constricted conditions. A set of the experiments of transmission of acoustic vibration to various points of the vessel was performed utilizing the half scale-hydraulic flow test facility simulating reactor vessel over the frequency range 20 kHz -- 100 kHz. Acoustic signals from an installed sound source in the core were measured at each point by both hydrophones in the vessel and vibration pickups on the vessel wall. In these experiments transmission of signals to each point of detectors were clearly observed to background noise level. These data have been summarized in terms of the transmission loss and furthermore are compared with background noise level of flow to estimate the feasibility of detection of sodium boiling sound. The ratio of signal to noise was obtained to be about 13 dB by hydrophone in the upper structure, 8 dB by accelerometer and 16 dB by AE-sensor at the upper position on the vessel in experiments used the simulation model. Sound waves emanated due to sodium boiling also propagate along the wall of the vessel may be predicted theoretically. The result of analysis suggests a capability of detection at the upper position of the reactor vessel wall. Leaky Lamb waves of the first symmetric (L 1 ) and of the antisymmetric (F 1 ) mode and shear horizontal wave (SH) have been derived in light of the attenuation due to coupling to liquid sodium as the traveling modes over the frequency range 10 kHz -- 100 kHz up to 50 mm in thickness of the vessel wall. Leaky Lamb wave (L 1 ) and (SH) mode have been proposed theoretically on the some assumption to be most available to detect the boiling sound of sodium propagating along the vessel wall. (author)

  18. Seventeen years of LMFBR experience: Experimental Breeder Reactor II (EBR-II)

    International Nuclear Information System (INIS)

    Perry, W.H.; Lentz, G.L.; Richardson, W.J.; Wolz, G.C.

    1982-01-01

    Operating experience at EBR-II over the past 17 years has shown that a sodium-cooled pool-type reactor can be safely and efficiently operated and maintained. The reactor has performed predictably and benignly during normal operation and during both unplanned and planned plant upsets. The duplex-tube evaporators and superheaters have never experienced a sodium/water leak, and the rest of the steam-generating system has operated without incident. There has been no noticeable degradation of the heat transfer efficiency of the evaporators and superheaters, except for the one superheater replaced in 1981. There has been no need to perform any chemical cleaning of steam-system components

  19. NACOWA experiments on LMFBR cover gas aerosols, heat transfer, and fission product enrichment

    International Nuclear Information System (INIS)

    Minges, J.; Schuetz, W.

    1993-12-01

    Fifteen different NACOWA test series were carried out. The following items were investigated: sodium mass concentration in the cover gas, sodium aerosol particle size, radiative heat transfer across the cover gas, total heat transfer across the cover gas, sodium deposition on the cover plate, temperature profiles across the cover gas, phenomena if the argon cover gas is replaced by helium, enrichment of cesium, iodine, and zinc in the aerosol and in the deposits. The conditions were mainly related to the design parameters of the EFR. According to the first consistent design, a pool temperature of 545 C and a roof temperature of only 120 C were foreseen at a cover gas height of 85 cm. The experiments were carried out in a stainless steel test vessel of 0.6 m diameter and 1.14 m height. Pool temperature (up to 545 C), cover gas height (12.5 cm, 33 cm, and others), and roof temperature (from 110 C to 450 C) were the main parameters. (orig./HP) [de

  20. Frequency interpretation of hold-time experiments on high temperature low-cycle fatigue of steels for LMFBR

    International Nuclear Information System (INIS)

    Udoguchi, T.; Asada, Y.; Ichino, I.

    1975-01-01

    The effect of frequency or hold-time on the low-cycle fatigue strength of AISI 316 stainless steel and SCM 3 Cr--Mo steel for fuel cladding, piping, and other structural members of LMFBR is investigated under high temperature conditions. Push-pull fatigue tests are conducted in air under conditions of fully reversed axial strain-control with a tensile strain hold-time ranging fromm 0 to 120 min for AISI 316, and with a tensile and an equal compressive strain hold-time ranging from 0 to 995 s for SCM 3. In these tests, a decrease of fatigue life is observed as the hold-time is increased. An empirical formula is presented which can predict well the effect of hold-time on high temperature low-cycle fatigue life in terms of frequency. The formula is a little different from those in the literature

  1. A frequency interpretation of hold-time experiments on high temperature low-cycle fatigue of steels for LMFBR

    International Nuclear Information System (INIS)

    Udoguchi, T.; Asada, Y.; Ichino, I.

    1975-01-01

    The effect of frequency or hold-time on the low-cycle fatigue strength of AISI 316 stainless steel and SCM 3 Cr-Mo steel for fuel cladding, piping and other structural members of LMFBR is investigated under high temperature conditions. Push-pull fatigue tests are conducted in air under conditions of fully reversed axial strain-control with a tensile strain hold-time ranging from 0 to 120 min for AISI 316, and with a tensile and an equal compressive strain hold-time ranging from 0 to 995 s for SCM 3. In these tests, a considerable decrease of fatigue life is observed as the hold-time is increased. An empirical formula is presented which can predict well the effect of hold-time on high temperature low-cycle fatigue life in terms of frequency. The formula is a little different from those in the literature. (author)

  2. In-pile observations of fuel and clad relocation during LMFBR initiation phase accident experiments - the STAR experiments

    International Nuclear Information System (INIS)

    Wright, S.A.; Schumacher, G.; Henkel, P.R.; Royl, P.

    1987-01-01

    A series of seven in-pile experiments (the STAR experiments) were performed in which clad motion and fuel dispersal were observed in small pin bundles with high-speed cinematography. The experimental heating conditions reproduced a range of Loss of Flow (LOF) accident scenarios for the lead subassemblies in LMFBRs. The experiments show strong tendencies for limited clad motion in multiple pin bundles, early fuel disruption and dispersal (prior to fuel melting) in moderate power transients having simultaneous clad melting and fuel disruption. The more recent experiments indicate a possibility of steel vapor driven fuel dispersal after fuel breakup and intimate fuel/steel mixing. (author)

  3. LMFBR: safety aspects

    International Nuclear Information System (INIS)

    Natta, M.

    1990-01-01

    This presentation of LMFBR safety is limited at Super Phenix reactor. After a brief description of the reactor, some details on safety systems, in normal or accidental conditions, are given. The main functions studied are: chain reaction trip, residual power evacuation, reactor containment. In heavy accident the behaviour of Super Phenix is studied which its particular characteristics and the possibilities of operators reactions. The probability of appearance and the maximum consequences of heavy accidents are given [fr

  4. LMFBR type reactor

    International Nuclear Information System (INIS)

    Kumaoka, Yoshio; Kawamura, Yutaka.

    1990-01-01

    A main vessel support skirt is supported by a base mat of reactor buildings and the base mat is supported by means of an earthquake-proof device on concretes of a lower raft disposed on ground rocks. The earthquake-proof device is constituted by alternately stacking, laminating and press-bonding thin steel plates together with thin rubber layers between an upper flange and a lower raft. Thus, for the horizontal seismic vibrations, the period of the swinging in the horizontal direction of the buildings is made greater than the swinging period of earthquakes by the earthquake-proof device to reduce the impact shocks of earthquakes. Further, for the vertical seismic vibrations, the input seismic movements are not amplified during transmission from the base mat of the buildings to the reactor structure by way of the support skirt of the main vessel, due to the shortened load transmission path and the seismic power design to the reactor structure can be moderated sufficiently. A safety LMFBR type reactor with reduced construction cost and improved reliability can be attained. (N.H.)

  5. LMFBR type reactor

    International Nuclear Information System (INIS)

    Masumi, Ryoji; Kawashima, Katsuyuki; Kurihara, Kunitoshi.

    1988-01-01

    Purpose: To flatten the power distribution while maintaining the flattening in the axial power distribution in LMFBR type reactors. Constitution: Main system control rods are divided into control rods used for the operation and starting rods used for the starting of the reactor, and the starting rods are disposed in the radial periphery of the reactor core, while the control rods are disposed to the inside of the starting rods. With such a constitution, adjusting rods can be disposed in the region where the radial power peaking is generated to facilitate the flattening of the power distribution even in such a design that the ratio of the number of control rods to that of fuel assemblies is relatively large. That is, in this reactor, the radial power peaking is reduced by about 10% as compared with the conventional reactor core. As a result, the maximum linear power density during operation is reduced by about 10% to increase the thermal margin of the reactor core. If the maximum linear power density is set identical, the number of the fuel assemblies can be decreased by about 10%, to thereby reduce the fuel production cost. (K.M.)

  6. P4-ATPases

    DEFF Research Database (Denmark)

    Lopez Marques, Rosa Laura; Theorin, Lisa; Palmgren, Michael Broberg

    2014-01-01

    Cellular membranes, notably eukaryotic plasma membranes, are equipped with special proteins that actively translocate lipids from one leaflet to the other and thereby help generate membrane lipid asymmetry. Among these ATP-driven transporters, the P4 subfamily of P-type ATPases (P4-ATPases......-ATPases differ in their substrate specificities and mediate transport of a broader range of lipid substrates, including lysophospholipids and synthetic alkylphospholipids. At the same time, the cellular processes known to be directly or indirectly affected by this class of transporters have expanded...... to include the regulation of membrane traffic, cytoskeletal dynamics, cell division, lipid metabolism, and lipid signaling. In this review, we will summarize the basic features of P4-ATPases and the physiological implications of their lipid transport activity in the cell....

  7. Accident considerations in LMFBR design

    International Nuclear Information System (INIS)

    Simpson, D.E.; Alter, H.; Fauske, H.K.; Hikido, K.; Keaten, R.W.; Stevenson, M.G.; Strawbridge, L.

    1975-12-01

    LMFBR safety design criteria are discussed from the standpoints of accident severity classification and damage criteria, and the following design events are considered: fuel failure propagation, reactivity addition faults, heat transport system events, steam generator faults, sodium spills, fuel handling and storage faults, and external events

  8. Transport-diffusion comparisons for small core LMFBR disruptive accidents

    International Nuclear Information System (INIS)

    Tomlinson, E.T.

    1977-11-01

    A number of numerical experiments were performed to assess the validity of diffusion theory for calculating the reactivity state of various small core LMFBR disrupted geometries. The disrupted configurations correspond, in general, to various configurations predicted by SAS3A for transient undercooling (TUC) and transient overpower (TOP) accidents for homogeneous cores and to the ZPPR-7 configurations for heterogeneous core. In all TUC cases diffusion theory was shown to be inadequate for the calculation of reactivity changes during core disassembly

  9. Hockey-stick steam generator for LMFBR

    International Nuclear Information System (INIS)

    Hallinan, G.J.; Svedlund, P.E.

    1981-01-01

    This paper presents the criteria and evaluation leading to the selection of the Hockey Stick Steam Generator Concept and subsequent development of that concept for LMFBR application. The selection process and development of the Modular Steam Generator (MSG) is discussed, including the extensive test programs that culminated in the manufacture and test of a 35 MW(t) Steam Generator. The design of the CRBRP Steam Generator is described, emphasizing the current status and a review of the critical structural areas. CRBRP steam generator development tests are evaluated, with a discussion of test objectives and rating of the usefulness of test results to the CRBRP prototype design. Manufacturing experience and status of the CRBRP prototype and plant units is covered. The scaleup of the Hockey Stick concept to large commercial plant application is presented, with an evaluation of scaleup limitations, transient effects, and system design implications

  10. Hydrogen jet recombination under postulated LMFBR accident conditions

    International Nuclear Information System (INIS)

    Wierman, R.W.

    1977-01-01

    Certain conditions may be postulated in LMFBR risk assessments for which the potential of hydrogen release to the reactor containment building needs to be evaluated. The inherent self-ignition characteristics of hydrogen jets entering the air atmosphere of the reactor containment building should be understood for such analyses. If hydrogen jets were to self-ignite (recombine) at the source where they enter the reactor containment building, then undesirable hydrogen accumulation would not occur. Therefore, experiments have been conducted investigating the phenomena associated with the recombination of hydrogen jets under conditions similar to those postulated for LMFBR studies. The data presented define the conditions required for self-ignition of the hydrogen jets

  11. Use of reliability in the LMFBR industry

    International Nuclear Information System (INIS)

    Penland, J.R.; Smith, A.M.; Goeser, D.K.

    1977-01-01

    This mission of a Reliability Program for an LMFBR should be to enhance the design and operational characteristics relative to safety and to plant availability. Successful accomplishment of this mission requires proper integration of several reliability engineering tasks--analysis, testing, parts controls and program controls. Such integration requires, in turn, that the program be structured, planned and managed. This paper describes the technical integration necessary and the management activities required to achieve mission success for LMFBR's

  12. Welding development for LMFBR applications

    International Nuclear Information System (INIS)

    Slaughter, G.M.; Edmonds, D.P.; Goodwin, G.M.; King, J.F.; Moorhead, A.J.

    1976-01-01

    High-quality welds with suitable properties for long-time elevated-temperature nuclear service are among the most critical needs in today's welding technology. Safe, reliable, and economic generation of future power depends on welded construction in systems such as Liquid Metal Fast Breeder Reactors (LMFBRs). Rapid thermal transients in LMFBR systems at coolant temperatures around 590 to 650 0 C (1000 to 1200 0 F) could cause creep and creep-fatigue damage that is not encountered in lower temperature reactor systems. The undesirable consequences of interaction between the two working fluids - sodium and steam - in the steam generators are also of major concern. Thus sound welds that have excellent reliability over a 30-year service life are essential. Several programs are actively underway at ORNL to satisfy this critical need and selected portions of three of these programs are discussed briefly

  13. Flow-induced vibration in LMFBR steam generators: a state-of-the-art review

    International Nuclear Information System (INIS)

    Shin, Y.S.; Wambsganss, M.W.

    1975-05-01

    This state-of-the-art review identifies and discusses existing methods of flow-induced vibration analysis applicable to steam generators, their limitations, and base-technology needs. Also included are discussions of five different LMFBR steam-generator configurations and important design considerations, failure experiences, possible flow-induced excitation mechanisms, vibration testing, and available methods of vibration analysis. The objectives are to aid LMFBR steam-generator designers in making the best possible evaluation of potential vibration in steam-generator internals, and to provide the basis for development of design guidelines to avoid detrimental flow-induced vibration

  14. Comparative analysis of LMFBR licensing in the United States and other countries - notably France. Executive summary

    International Nuclear Information System (INIS)

    Golay, M.W.; Castillo, M.

    1981-01-01

    The safety-related design aspects and licensing experiences of LMFBR projects in other democratic countries have been studied and contrasted to those in the United States in order to understand the importance of different approaches to safety, and also to understand better the system of the United States. The regulatory systems and LMFBR programs of France and the United States are contrasted in detail, and that of West Germany is also studied. The programs of Japan and the United Kingdom receive considerably less attention, and that of the Soviet Union is ignored

  15. Upon local blockage formations in LMFBR fuel rod bundles with wire-wrapped spacers

    International Nuclear Information System (INIS)

    Minden, C. v.; Schultheiss, G.F.

    1982-01-01

    A theoretical and experimental study, to improve understanding of local particle depositions in a wire-wrapped LMFBR fuel bundle, has been performed. Theoretical considerations show, that a preferentially axial process of particle depositions occurs. The experiments confirm this and clarify that the blockages arise near the particle source and settle at the spatially arranged minimum gaps in the bundle. The results suggest that, considering flow reduction, cooling and DND-detection, such fuel particle blockages are less dangerous. With reference to these safety-relevant factors, wire-wrapped LMFBR fuel bundles seem to gain advantages compared to the grid design. (orig.) [de

  16. Fission and corrosion products behavior in primary circuits of LMFBR's

    International Nuclear Information System (INIS)

    Feuerstein, H.; Thorley, A.W.

    1987-08-01

    Most of the 20 presented papers report items belonging to more than one session. The equipment results of primary circuits of LMFBR's relative to corrosion and fission products, release and chemistry of fuel, measurement techniques and analytical procedures of sodium sampling, difficulties with radionuclides and particles, reactor experiences with EBR-II, FFTF, BR10, BOR60, BN350, BN600, JOYO, and KNK-II, DFR, PFR, RAPSODIE, PHENIX, and SUPERPHENIX, and at least the verification of codes for calculation models of radioactive products accumulation and distribution are described. All 20 papers presented at the meeting are separately indexed in the database. (DG)

  17. Coolant mixing in the LMFBR outlet plenum

    International Nuclear Information System (INIS)

    Chen, Y.B.; Golay, M.W.

    1977-06-01

    Small scale experiments involving water flows are used to provide mean flow and turbulence field data for LMFBR outlet plenum flows. Measurements are performed at Reynolds Number (Re) values of 33000 and 70000 in a 1/15-scale FFTF geometry and at Re = 35000 in a 3/80-scale CRBR geometry. The experimental behavior is predicted using two different turbulence model computer programs, TEACH-T and VARR-II. It is found that the qualitative nature of the flow field within the plenum depends strongly upon the distribution of the mean inlet velocity field, upon the degree of inlet turbulence, and upon the turbulence momentum exchange model used in the calculations. It is found in the FFTF geometry that the TEACH-T predictions are better than that of VARR-II, and in the CRBR geometry neither code provides a good prediction of the observed behavior. From the sensitivity analysis, it is found that the production and dissipation of turbulence are the dominant terms in the transport equations for turbulent kinetic energy and turbulent energy dissipation rate, and the diffusion terms are relatively small. From the same study a new set of empirical constants for the turbulence model is evolved for the prediction of plenum flows

  18. Performance analysis of LMFBR control rods

    International Nuclear Information System (INIS)

    Pitner, A.L.; Birney, K.R.

    1975-01-01

    Control rods in the FFTF and LMFBR's will consist of pin bundles of stainless steel-clad boron carbide pellets. In the FFTF reference design, sixty-one pins of 0.474-inch diameter each containing a 36-inch stack of 0.362-inch diameter boron carbide pellets comprise a control rod. Reactivity control is provided by the 10 B (n,α) 7 Li reaction in the boron carbide. This reaction is accompanied by an energy release of 2.8 MeV, and heating from this reaction typically approaches 100 watts/cm 3 for natural boron carbide pellets in an LMFBR flux. Performance analysis of LMFBR control rods must include an assessment of the thermal performance of control pins. In addition, irradiation performance with regard to helium release, pellet swelling, and reactivity worth depletion as a function of service time must be evaluated

  19. Perfomance analysis of boron carbide in LMFBR

    International Nuclear Information System (INIS)

    Pitner, A.L.; Birney, K.R.

    1975-01-01

    Reactivity control in the FFTF and LMFBR's will be maintained by control elements utilizing boron carbide pellets contained in stainless steel pins. Computer performance codes predict irradiation service conditions of absorber pellets and identify required experimental testing. Test results are incorporated in the codes to improve performance prediction capabilities

  20. P4 Medicine versus Hippocrates.

    Science.gov (United States)

    Pulciani, Simonetta; Di Lonardo, Anna; Fagnani, Corrado; Taruscio, Domenica

    2017-01-01

    Hippocrates was the first to raise awareness of medicine as a science. He asserted the body being a unified whole and emphasized the importance of preventive and predictive medicine, spurring physicians to foster patient collaboration. Recent achievements today have permitted a new approach "P4 medicine" - Predictive, Preventive, Personalized and Participatory - with the aim of depicting an individual's health history and molecular profile in determining the best medical intervention in maintaining or restoring wellbeing. There is a link, which brings together Hippocrates and P4 Medicine. This review will elaborate further this statement, considering the scientific achievements that paved the way for recent medical approaches. Emphasis will be given to the social impact of new diagnostic and therapeutic protocols, considering their costs and their success probabilities.

  1. A note on p-groups of order≤ p4p4p4

    Indian Academy of Sciences (India)

    A Note on -Groups of Order ≤ p 4. Houshang Behravesh Hamid Mousavi. Volume 119 Issue 2 April 2009 pp 137-143. Fulltext. Click here to view fulltext PDF. Permanent link: http://www.ias.ac.in/article/fulltext/pmsc/119/02/0137-0143. Keywords. Quasi-permutation representations; -groups; character theory.

  2. Reliable measurement of the Li-like 2248Ti 1s2s2p 4P5/2o level lifetime by beam-foil and beam-two-foil experiments

    International Nuclear Information System (INIS)

    Nandi, T.; Ahmad, Nissar; Wani, A. A.; Marketos, P.

    2006-01-01

    We have determined the lifetime of the Li-like 22 48 Ti 1s2s2p 4 P 5/2 o level (210.5±13.5 ps) using data from its x-ray decay channel through beam single- and two-foil experiments, coupled to a multicomponent iterative growth and decay analysis. Theoretical lifetime estimates for this zero-nuclear-spin ion lies within the uncertainty range of our experimental results, indicating that blending contributions to this level from the He-like 1s2p 3 P 2 o and 1s2s 3 S 1 levels are eliminated within the current approach. A previously reported discrepancy between experimental and theoretical 1s2s2p 4 P 5/2 o level lifetimes in 23 51 V may, as a result, be attributed to hyperfine quenching

  3. LMFBR steam generators in the United Kingdom

    International Nuclear Information System (INIS)

    Anderson, R.; Hayden, O.

    2002-01-01

    Experience has been gained in the UK on the operation of LMFBR Steam Generator Units (SGU) over a period of 20 years from the Dounreay Fast Reactor (DFR) and the Prototype Fast Reactor (PFR). The DFR steam generator featured a double barrier and therefore did not represent a commercial design. PFR, however, faced the challenge of a single wall design and it is experience from this which is most valuable. The PFR reactor went critical in March 1974 and the plant operating history since then has been dominated by experience with leaks in the tube to tube plate welds of the high performance U-tubes SGU's. Operation at high power using the full complement of three secondary sodium circuits was delayed until July 1976 by the occurrence of leaks in the tube to tube plate welds of the superheater and reheater units which are fabricated in stainless steel. Repairs were carried out to the two superheaters and they were returned to service. The reheater tube bundle was removed from circuit after sodium was found to have entered the steam side. When the sodium had been removed and inspection carried out it was decided not to recover the unit. Since 1976 the remaining five stainless steel units have operated satisfactorily. This year a replacement reheater unit has been installed. This is of a new design in 9-Cr-Mo ferritic steel using a sleeve through which the steam tube passes to eliminate the tube to tube plate weld. Despite a few early leaks in evaporator tube to tube plate welds up to 1979, these failures did not initially present a major problem. However, in 1980 the rate of evaporator weld failures increased and despite the successful application of a shot peening process to eliminate stress corrosion failures from the water side of the weld, failures traced to the sodium side continued. A sleeving process was developed for application to complete evaporator units on a production basis with the objective of bypassing the welds at each end of the 500 tubes. The decision

  4. Hot clamp design for LMFBR piping systems

    International Nuclear Information System (INIS)

    Kobayashi, T.; Tateishi, M.

    1993-01-01

    Thin-wall, large-diameter piping for liquid metal fast breeder reactor (LMFBR) plants can be subjected to significant thermal transients during reactor scrams. To reduce local thermal stresses, an insulated cold clamp was designed for the fast flux test facility and was also applied to some prototype reactors thereafter. However, the cost minimization of LMFBR requires much simpler designs. This paper presents a hot clamp design concept, which uses standard clamp halves directly attached to the pipe surface leaving an initial gap. Combinations of flexible pipe and rigid clamp achieved a self-control effect on clamp-induced pipe stresses due to the initial gap. A 3-D contact and inelastic history analysis were performed to verify the hot clamp concept. Considerations to reduce the initial stress at installation, to mitigate the clamp restraint on the pipe expansion during thermal shocks, and to maintain the pipe-clamp stiffness desired during a seismic event were discussed

  5. LMFBR with booster pump in pumping loop

    International Nuclear Information System (INIS)

    Rubinstein, H.J.

    1975-01-01

    A loop coolant circulation system is described for a liquid metal fast breeder reactor (LMFBR) utilizing a low head, high specific speed booster pump in the hot leg of the coolant loop with the main pump located in the cold leg of the loop, thereby providing the advantages of operating the main pump in the hot leg with the reliability of cold leg pump operation

  6. Chemical factors affecting fission product transport in severe LMFBR accidents

    International Nuclear Information System (INIS)

    Wichner, R.P.; Jolley, R.L.; Gat, U.; Rodgers, B.R.

    1984-10-01

    This study was performed as a part of a larger evaluation effort on LMFBR accident, source-term estimation. Purpose was to provide basic chemical information regarding fission product, sodium coolant, and structural material interactions required to perform estimation of fission product transport under LMFBR accident conditions. Emphasis was placed on conditions within the reactor vessel; containment vessel conditions are discussed only briefly

  7. Chemical factors affecting fission product transport in severe LMFBR accidents

    Energy Technology Data Exchange (ETDEWEB)

    Wichner, R.P.; Jolley, R.L.; Gat, U.; Rodgers, B.R.

    1984-10-01

    This study was performed as a part of a larger evaluation effort on LMFBR accident, source-term estimation. Purpose was to provide basic chemical information regarding fission product, sodium coolant, and structural material interactions required to perform estimation of fission product transport under LMFBR accident conditions. Emphasis was placed on conditions within the reactor vessel; containment vessel conditions are discussed only briefly.

  8. Specialists' meeting on maintenance and repair of LMFBR steam generators. Summary report

    International Nuclear Information System (INIS)

    2002-01-01

    The purpose of the meeting was to review and discuss the experience accumulated in various countries on the general design philosophy of LMFBR steam generators from the view point of maintenance and repair, in-service inspection of steam generator tube bundles, identification and inspection of failed tubes and the cleaning and repairing of failed steam generators. The following main topic areas were discussed by participants: National review presentations on maintenance and repair of LMFBR steam generators - design philosophy for maintenance and repair; Research and Development work on maintenance and repair; Experience on steam generator maintenance and repair. During the meeting papers were presented by the participants on behalf of their countries and organizations. A final discussion session was held and summaries, general conclusions and recommendations were approved by consensus

  9. Issues in the selection of the LMFBR steam cycle

    International Nuclear Information System (INIS)

    Buschman, H.W.; McConnell, R.J.

    1983-01-01

    Unlike the light-water reactor, the liquid-metal fast breeder reactor (LMFBR) allows the designer considerable latitude in the selection of the steam cycle. This latitude in selection has been exercised by both foreign and domestic designers, and thus, despite the fact that over 25 LMFBR's have been built or are under construction, a consensus steam cycle has not yet evolved. This paper discusses the LMFBR steam cycles of interest to the LMFBR designer, reviews which of these cycles have been employed to date, discusses steam-cycle selection factors, discusses why a consensus has not evolved, and finally, concludes that the LMFBR steam-cycle selection is primarily one of technical philosophy with several options available

  10. Specialists meeting on leak detection and location in LMFBR steam generators. Summary report

    International Nuclear Information System (INIS)

    1978-10-01

    The following topics covered at the meeting were: with leak detection and location methods and equipment, including concentration measurements, helium tests, and electromagnetic methods; acoustic leak detection and related equipment; techniques and experiences in ensuring and measuring steam generator tightness during manufacturing, installation and repair, tube inspection methods for periodic control and damage assessment following leaks, influence of these methods on design of steam generators for LMFBR type reactors

  11. Compatibility of niobium, titanium, and vanadium metals with LMFBR cladding

    International Nuclear Information System (INIS)

    Wilson, C.N.

    1975-10-01

    A series of laboratory capsule annealing experiments were conducted to assess the compatibility of niobium, vanadium, and titanium with 316 stainless steel cladding in the temperature range of 700 to 800 0 C. Niobium, vanadium, and titanium are cantidate oxygen absorber materials for control of oxygen chemistry in LMFBR fuel pins. Capsule examination indicated good compatibility between niobium and 316 stainless steel at 800 0 C. Potential compatibility problems between cladding and vanadium or titanium were indicated at 800 0 C under reducing conditions. In the presence of Pu/sub 0.25/U/sub 0.75/O/sub 1.98/ fuel (Δanti G 02 congruent to -160 kcal/mole) no reaction was observed between vanadium or titanium and cladding at 800 0 C

  12. Evaluation of LMFBR fuel-motion diagnostics instrumentation with PARKA

    International Nuclear Information System (INIS)

    Evans, A.E. Jr.; Orndoff, J.D.; Talbert, W.L. Jr.

    1978-01-01

    To aid in the design of LMFBR safety test experiments and safety test facilities (STF), a program of evaluation of concepts for fuel-motion diagnostics instrumentation has been undertaken. A part of this evaluation is beng done at PARKA, a Rover project critical assembly which has been modified to study the self nuclear image from driven FTR-type fuel assemblies. Feasibility of obtaining fast-neutron images of single-pin voids in assemblies of up to 127 fuel pins has been demonstrated, albeit marginally for the larger fuel bundles. The feasibility of using in-core detectors as fuel-motion monitors has also been studied. Use of PARKA in a pulsed mode to study STF transient phenomena is discussed

  13. Overview of the fast reactors fuels program. [LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Evans, E.A.; Cox, C.M.; Hayward, B.R.; Rice, L.H.; Yoshikawa, H.H.

    1980-04-01

    Each nation involved in LMFBR development has its unique energy strategies which consider energy growth projections, uranium resources, capital costs, and plant operational requirements. Common to all of these strategies is a history of fast reactor experience which dates back to the days of the Manhatten Project and includes the CLEMENTINE Reactor, which generated a few watts, LAMPRE, EBR-I, EBR-II, FERMI, SEFOR, FFTF, BR-1, -2, -5, -10, BOR-60, BN-350, BN-600, JOYO, RAPSODIE, Phenix, KNK-II, DFR, and PFR. Fast reactors under design or construction include PEC, CRBR, SuperPhenix, SNR-300, MONJU, and Madras (India). The parallel fuels and materials evolution has fully supported this reactor development. It has involved cermets, molten plutonium alloy, plutonium oxide, uranium metal or alloy, uranium oxide, and mixed uranium-plutonium oxides and carbides.

  14. Compatibility of niobium, titanium, and vanadium metals with LMFBR cladding

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, C.N.

    1975-10-01

    A series of laboratory capsule annealing experiments were conducted to assess the compatibility of niobium, vanadium, and titanium with 316 stainless steel cladding in the temperature range of 700 to 800/sup 0/C. Niobium, vanadium, and titanium are cantidate oxygen absorber materials for control of oxygen chemistry in LMFBR fuel pins. Capsule examination indicated good compatibility between niobium and 316 stainless steel at 800/sup 0/C. Potential compatibility problems between cladding and vanadium or titanium were indicated at 800/sup 0/C under reducing conditions. In the presence of Pu/sub 0.25/U/sub 0.75/O/sub 1.98/ fuel (..delta..anti G/sub 02/ congruent to -160 kcal/mole) no reaction was observed between vanadium or titanium and cladding at 800/sup 0/C.

  15. Shielding plug for LMFBR type reactors

    International Nuclear Information System (INIS)

    Hashiguchi, Ko.

    1979-01-01

    Purpose: To enable effective removal of liquid metals deposited, if any, in the gaps between a rotary plug and a fixed plug in LMFBR type reactors. Constitution: A plate incorporated with a heater and capable of projecting in a gap between a rotary plug and a fixed plug, and a scraper connected in perpendicular to it are provided to the rotary plug. Solidified liquid metals such as sodium deposited in the gap are effectively removed by the heating with the heater and the scraping action due to the rotation. (Horiuchi, T.)

  16. CEC activities in the field of LMFBR safety

    International Nuclear Information System (INIS)

    Balz, W.; Finzi, S.; Klersy, R.

    1976-01-01

    The aim of the ECC is to reach a common LMFBR Safety strategy in Europe. To this end the Commission promotes collaboration between the different fast reactor projects in the Community through working groups and collaborative arrangements and contributes with a research activity executed in its Joint Research Centre Ispra. A short description is given of the activity in the working groups and of the Ispra programme on LMFBR Safety. This programme covers: LMFBR thermohydraulics, fuel coolant interactions, dynamic structure loading and response, safety related material properties and whole core accident code development

  17. Ferritic steels for French LMFBR steam generators

    International Nuclear Information System (INIS)

    Aubert, M.; Mathieu, B.; Petrequin, P.

    1983-06-01

    Austenitic stainless steels have been widely used in many components of the French LMFBR. Up to now, ferritic steels have not been considered for these components, mainly due to their relatively low creep properties. Some ferritic steels are usable when the maximum temperatures in service do not exceed about 530 0 C. It is the case of the steam generators of the Phenix plant, where the exchange tubes of the evaporator are made of 2,25% Cr-1% Mo steel, stabilized or not by addition of niobium. These ferritic alloys have worked successfully since the first steam production in October 1973. For the SuperPhenix power plant, an ''all austenitic stainless alloy'' apparatus has been chosen. However, for the future, ferritic alloys offer potential for use as alternative materials in the evaporators: low alloys steels type 2,25% Cr-1% Mo (exchange tubes, tube-sheets, shells), or at higher chromium content type 9% Cr-2% Mo NbV (exchange tubes) or 12M Cr-1% Mo-V (tube-sheets). Most of these steels have already an industrial background, and are widely used in similar applications. The various potential applications of these steels are reviewed with regards to the French LMFBR steam generators, indicating that some points need an effort of clarification, for instance the properties of the heterogeneous ferritic/austenitic weldments

  18. Maintenance and repair of LMFBR steam generators: specialists` meeting, O-Arai Engineering Center, Japan, 4-8 June 1984. Summary report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1984-07-01

    The Specialists` Meeting on "Maintenance and Repair of LMFBR Steam Generators" was held in Oarai, Japan, from 4-8 June 1984. The meeting was sponsored by the International Atomic Energy Agency on the recommendation of the IAEA International Working Group on Fast Reactors and was hosted by the Power Reactor and Nuclear Fuel Development Corporation of Japan. The purpose of the meeting was to review and discuss the experience accumulated in various countries on the general design philosophy of LMFBR steam generators from the view point of maintenance and repair, in-service inspection of steam generator tube bundles, identification and inspection of failed tubes and the cleaning and repairing of failed steam generators. The following main topical areas were discussed by participants: national review presentations on maintenance and repair of LMFBR steam generators - design philosophy for maintenance and repair; research and development work on maintenance and repair; and experience on steam generator maintenance and repair.

  19. LMFBR subassembly response to local pressure loadings: an experimental approach

    International Nuclear Information System (INIS)

    Marciniak, T.J.; Ash, J.E.; Marchertas, A.H.; Cagliostro, D.J.

    1975-01-01

    An experimental program to determine the response of LMFBR-type subassemblies to local subassembly accidents caused by pressure loadings is described. Some results are presented and compared with computer calculations

  20. Status of U.S. LMFBR programme

    International Nuclear Information System (INIS)

    Yevich, J.

    1978-01-01

    The determents of the decision for deterrence of commercial reprocessing and further demonstration of the plutonium breeder were based on two premises: time is needed to establish the programme for non-proliferating fuel cycle and there is a lessened sense of urgency for the USA to establish a commercial breeder in the near future. A strong, well funded base technology effort remains and will continue until institutional and technical solutions can be found to minimize or eliminate the proliferation risk. An LMFBR option will be maintained. The FFTF will be coming on line providing a powerful tool in breeder fuel and materials development and a baseline from which to scale up heat transfer systems and components. Sodium system hardware development and testing will continue to have high priority

  1. Acoustic leak detection of LMFBR steam generator

    International Nuclear Information System (INIS)

    Kumagai, Hiromichi; Yoshida, Kazuo

    1993-01-01

    The development of a water leak detector with short response time for LMFBR steam generators is required to prevent the failure propagation caused by the sodium-water reaction and to maintain structural safety in steam generators. The development of an acoustic leak detector assuring short response time has attracted. The purpose of this paper is to confirm the basic detection feasibility of the active acoustic leak detector, and to investigate the leak detection method by erasing the background noise by spectrum analysis of the passive acoustic leak detector. From a comparison of the leak detection sensitivity of the active and the passive method, the active method is not influenced remarkably by the background noise, and it has possibility to detect microleakage with short response time. We anticipate a practical application of the active method in the future. (author)

  2. Nuclear welding, application for an LMFBR

    International Nuclear Information System (INIS)

    Patriarca, P.; Goodwin, G.M.

    1975-01-01

    Fabrication of an LMFBR system is discussed, with emphasis on areas where joint welding innovations have been introduced. Each major component of the system, including reactor vessel, intermediate heat exchanger, steam generator, and sodium-containment piping, is treated separately. Developmet of special filler metals to avoid the low elevated-temperature creep ductility obtained with conventional austenitic stainless steel weldments is reported. Bore-side welding of steam generator tube-to-tubesheet joints with and without filler metal is desirable to improve inspectability and eliminate the crevice inherent with face-side weld design, thus minimizing corrosion problems. Automated welding methods for sodium-containment piping are summarized which iminimize and control distortion and ensure welds of high integrity. Selection of materials for the various components is discussed for plants presently under construction, and materials predictions are made for future concepts. (U.S.)

  3. Low cycle fatigue of irradiated LMFBR materials

    International Nuclear Information System (INIS)

    Blackburn, L.D.

    1976-01-01

    A review of low cycle fatigue data on irradiated LMFBR materials was conducted and extensive graphical representations of available data are presented. Representative postirradiation tensile properties of annealed 304 and 316 SS are selected and employed in several predictive methods to estimate irradiated material fatigue curves. Experimental fatigue data confirm the use of predictive methods for establishing conservative design curves over the range of service conditions relevant to such CRBRP components as core former, fixed radial shielding, core barrel, lower inlet module and upper internals structures. New experimental data on fatigue curves and creep-fatigue interaction in irradiated 20 percent cold worked (CW) 316 SS and Alloy 718 would support the design of removable radial shielding and upper internals in CRBRP. New experimental information on notched fatigue behavior and cyclic stress-strain curves of all these materials in the irradiated condition could provide significant design data

  4. Fueling method in LMFBR type reactors

    International Nuclear Information System (INIS)

    Kawashima, Katsuyuki; Inoue, Kotaro.

    1985-01-01

    Purpose: To extend the burning cycle and decrease the number of fuel exchange batches without increasing the excess reactivity at the initial stage of burning cycles upon fuel loading to an LMFBR type reactor. Method: Each of the burning cycles is divided into a plurality of burning sections. Fuels are charged at the first burning section in each of the cycles such that driver fuel assemblies and blanket assemblies or those assemblies containing neutron absorbers such as boron are distributed in mixture in the reactor core region. At the final stage of the first burning section, the blanket assemblies or neutron absorber-containing assemblies present in mixture are partially or entirely replaced with driver fuel assemblies depending on the number of burning sections such that all of them are replaced with the driver fuel assemblies till the start of the final burning section of the abovementioned cycle. The object of this invention can thus be attained. (Horiuchi, T.)

  5. Microprocessor-based integrated LMFBR core surveillance

    International Nuclear Information System (INIS)

    Gmeiner, L.

    1984-06-01

    This report results from a joint study of KfK and INTERATOM. The aim of this study is to explore the advantages of microprocessors and microelectronics for a more sophisticated core surveillance, which is based on the integration of separate surveillance techniques. Due to new developments in microelectronics and related software an approach to LMFBR core surveillance can be conceived that combines a number of measurements into a more intelligent decision-making data processing system. The following techniques are considered to contribute essentially to an integrated core surveillance system: - subassembly state and thermal hydraulics performance monitoring, - temperature noise analysis, - acoustic core surveillance, - failure characterization and failure prediction based on DND- and cover gas signals, and - flux tilting techniques. Starting from a description of these techniques it is shown that by combination and correlation of these individual techniques a higher degree of cost-effectiveness, reliability and accuracy can be achieved. (orig./GL) [de

  6. Hot clamp design for LMFBR piping systems

    International Nuclear Information System (INIS)

    Kobayashi, T.; Tateishi, M.

    1990-01-01

    Thin wall large diameter piping for liquid metal fast breeder reactor plants can be subjected to significant thermal transients during reactor scrams. To reduce local thermal stresses, an insulted cold clamp was designed for the Fast Flux Test Facility and was also applied to some following prototype reactors. However, the cost minimization of LMFBR requires much simpler designs. This paper presents a hot clamp design concept, which uses standard clamp halves directly attached to the pipe surface with an initial gap. Combinations of flexible pipe and rigid clamp achieved a self-control effect on clamp induced pipe stresses due to the initial gap. A 3-D contact and inelastic history analysis were performed to verify the hot clamp concept. Considerations to reduce the initial stress at installation, to mitigate the clamp restraint on the pipe expansion during thermal shocks, and to maintain the pipe-clamp stiffness desired during a seismic event are discussed

  7. Operating temperatures for an LMFBR

    International Nuclear Information System (INIS)

    Bhoje, S.B.; Chellapandi, P.

    1993-01-01

    . Viscoplastic analysis should be carried out for control plug, intermediate heat exchanger and steam generator also. Experiments on simple structures which are incorporated with the necessary component features like weldments, multiaxiality, stress concentration etc. have to be performed to validate material modelling, analysis methodology and design criteria, in an overall basis

  8. PNC status report on leak detector development for LMFBR steam generators

    International Nuclear Information System (INIS)

    Kuroha, M.; Sato, M.

    1984-01-01

    Chemical and acoustic type leak detectors have been developed for detecting a small sodium-water reaction in an LMFBR steam generator. This paper presents a summary of the development. (1) Test results on PNC type in-sodium hydrogen meters including a description of the structure, the long-term reliability and the durability, and the improved meter with an orifice, (2) Development of in-cover gas hydrogen meters, (3) Hydrogen detection tests and analyses, (4) Operating experiences of electrochemical in-sodium oxygen meters, and (5) Basic studies on acoustic characteristics of the sodium-water reaction. (author)

  9. LMFBR safety. 1. Review of current issues and bibliography of literature, 1960--1969

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.; Keilholtz, G.W.

    1976-08-16

    This report discusses the current status of liquid-metal fast breeder (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1960 through 1969. The bibliography consists of 1560 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness.

  10. LMFBR safety. 4. Review of current issues and bibliography of literature (1974--1975)

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.; Keilholtz, G.W.

    1977-03-21

    This report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1974 through 1975. The bibliography consists of approximately 1554 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness.

  11. LMFBR safety. 2. Review of current issues and bibliography of literature, 1970--1972

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.; Keilholtz, G.W.

    1976-11-22

    This report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1970 through 1972. The bibliography consists of approximately 1620 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness.

  12. LMFBR safety. 3. Review of current issues and bibliography of literature (1972--1974)

    International Nuclear Information System (INIS)

    Buchanan, J.R.; Keilholtz, G.W.

    1977-01-01

    The report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1972 through 1974. The bibliography consists of approximately 1380 abstracts covering research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included

  13. LMFBR safety. 2. Review of current issues and bibliography of literature, 1970--1972

    International Nuclear Information System (INIS)

    Buchanan, J.R.; Keilholtz, G.W.

    1976-01-01

    This report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1970 through 1972. The bibliography consists of approximately 1620 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness

  14. LMFBR safety. 3. Review of current issues and bibliography of literature (1972--1974)

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.; Keilholtz, G.W.

    1977-02-24

    The report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1972 through 1974. The bibliography consists of approximately 1380 abstracts covering research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included.

  15. LMFBR safety. 4. Review of current issues and bibliography of literature (1974--1975)

    International Nuclear Information System (INIS)

    Buchanan, J.R.; Keilholtz, G.W.

    1977-01-01

    This report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1974 through 1975. The bibliography consists of approximately 1554 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness

  16. LMFBR safety. 5. Review of current issues and bibliography of literature (1975--1976)

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.; Keilholtz, G.W.

    1977-06-08

    The current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA), are discussed. Bibliographic information on worldwide LMFBRs relative to the development and safety of the breeder reactor is presented for the period 1975 through 1976. The bibliography consists of approximately 1618 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Keyword, author, and permuted-title indexes are included for completeness.

  17. LMFBR safety. 1. Review of current issues and bibliography of literature, 1960--1969

    International Nuclear Information System (INIS)

    Buchanan, J.R.; Keilholtz, G.W.

    1976-01-01

    This report discusses the current status of liquid-metal fast breeder (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1960 through 1969. The bibliography consists of 1560 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness

  18. Comments on US LMFBR steam generator base technology

    International Nuclear Information System (INIS)

    Simmons, W.R.

    1984-01-01

    The development of steam generators for the LMFBR was recognized from the onset by the AEC, now DOE, as a difficult, challenging, and high-priority task. The highly reactive nature of sodium with water/steam requires that the sodium-water/steam boundaries of LMFBR steam generators possess a degree of leak-tightness reliability not normally attempted on a commercial scale. In addition, the LMFBR steam generator is subjected to high fluid temperatures and severe thermal transients. These requirements place great demand on materials, fabrication processes, and inspection methods; and even greater demands on the designer to provide steam generators that can meet these demanding requirements, be fabricated without unreasonable shop requirements, and tolerate off-normal effects

  19. Hydrogen formation and control under postulated LMFBR accident conditions

    International Nuclear Information System (INIS)

    Armstrong, G.R.; Wierman, R.W.

    1976-09-01

    The objective of this study is to experimentally investigate the potential for autoignition and combustion of hydrogen-sodium mixtures which may be produced in LMFBR accidents. The purpose and ultimate usefulness of this work is to provide data that will establish the validity and acceptability of mechanisms inherent to the LMFBR that could either prevent or delay the accumulation of hydrogen gas to less than 4 percent (V) in the Reactor Containment Building (RCB) under accident conditions. The results to date indicate that sodium and sodium-hydrogen mixtures such as may be expected during LMFBR postulated accidents will ignite upon entering an air atmosphere and that the hydrogen present will be essentially all consumed until such time that the oxygen concentration is depleted

  20. Measurements of dynamic shape factors of LMFBR aggregate aerosols

    International Nuclear Information System (INIS)

    Allen, M.D.; Moss, O.R.; Briant, J.K.

    1980-01-01

    Dynamic shape factors for branched, chain-like aggregates of LMFBR mixed-oxide fuels have been measured with a LAPS spiral-duct centrifuge. The aerosol was generated by repeatedly pulsing a focused laser beam onto the surface of a typical LMFBR fuel pellet. The measured values of the dynamic shape factor, corrected for slip, vary between kappa = 3.60 at D/sub ae/ = 0.5 μm, and kappa = 2.23 at D/sub ae/ = 1.5 μm

  1. Status of gamma-ray heating characterization in LMFBR

    International Nuclear Information System (INIS)

    Gold, R.

    1975-11-01

    Efforts to define gamma-ray heating in Liquid Metal Fast Breeder Reactor (LMFBR) environments have been surveyed. Emphasis is placed on both current practice for the Experimental Breeder Reactor-II (EBR-II) and future needs of the Fast Flux Test Facility (FFTF). Experimental and theoretical work are included in this preliminary survey for both high and low power environments. Current ''state-of-the-art'' accuracies and limitations are assessed. On this basis, it is concluded that a broad and sustained effort be initiated to meet requested FFTF goal accuracies. To this end, recommendations are advanced for improving the current status of gamma heating characterization and temperature measurements in LMFBR

  2. Computer simulation of LMFBR piping systems

    International Nuclear Information System (INIS)

    A-Moneim, M.T.; Chang, Y.W.; Fistedis, S.H.

    1977-01-01

    Integrity of piping systems is one of the main concerns of the safety issues of Liquid Metal Fast Breeder Reactors (LMFBR). Hypothetical core disruptive accidents (HCDA) and water-sodium interaction are two examples of sources of high pressure pulses that endanger the integrity of the heat transport piping systems of LMFBRs. Although plastic wall deformation attenuates pressure peaks so that only pressures slightly higher than the pipe yield pressure propagate along the system, the interaction of these pulses with the different components of the system, such as elbows, valves, heat exchangers, etc.; and with one another produce a complex system of pressure pulses that cause more plastic deformation and perhaps damage to components. A generalized piping component and a tee branching model are described. An optional tube bundle and interior rigid wall simulation model makes such a generalized component model suited for modelling of valves, reducers, expansions, and heat exchangers. The generalized component and the tee branching junction models are combined with the pipe-elbow loop model so that a more general piping system can be analyzed both hydrodynamically and structurally under the effect of simultaneous pressure pulses

  3. Review of PRA methodology for LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Yang, J.E

    1999-02-01

    Probabilistic Risk Assessment (PRA) has been widely used as a tool to evaluate the safety of NPPs (Nuclear Power Plants), which are in the design stage as well as in operation. Recently, PRA becomes one of the licensing requirements for many existing and new NPPs. KALIMER is a Liquid Metal Fast Breeder Reactor (LMFBR) being developed by KAERI. Since the design concept of KALIMER is similar to that of the PRISM plant developed by GE, it would be appropriate to review the PRA methodology of PRISM as the first step of KALIMER PRA. Hence, in this report summarizes the PRA methodology of PRISM plant, and the required works for the PSA of KALIMER based on the reviewed results. The PRA technology of PRISM plant consists of following five major tasks: (1) development of initiating event list, (2) development of system event tree, (3) development of core response event tree, (4) development of containment response event tree, and (5) consequences and risk estimation. The estimated individual and societal risk measures show that the risk from a PRISM module is substantially less than the NRC goal. Each task is compared to the PRA methodology of Light Water Reactor (LWR)/Pressurized Heavy Water Reactor (PHWR). In the report, each task of PRISM PRA methodology is reviewed and compared to the corresponding part of LWR/PHWR PSA performed in Korea. The parts that are not modeled appropriately in PRISM PRA are identified, and the recommendations for KALIMER PRA are stated. (author). 14 refs., 9 tabs., 4 figs.

  4. Steam generating system in LMFBR type reactors

    International Nuclear Information System (INIS)

    Kurosawa, Katsutoshi.

    1984-01-01

    Purpose: To suppress the thermal shock loads to the structures of reactor system and secondary coolant system, for instance, upon plant trip accompanying turbine trip in the steam generation system of LMFBR type reactors. Constitution: Additional feedwater heater is disposed to the pipeway at the inlet of a steam generator in a steam generation system equipped with a closed loop extended from a steam generator by way of a gas-liquid separator, a turbine and a condensator to the steam generator. The separated water at high temperature and high pressure from a gas-liquid separator is heat exchanged with coolants flowing through the closed loop of the steam generation system in non-contact manner and, thereafter, introduced to a water reservoir tank. This can avoid the water to be fed at low temperature as it is to the steam generator, whereby the thermal shock loads to the structures of the reactor system and the secondary coolant system can be suppressed. (Moriyama, K.)

  5. Intelligent type sodium instrumentations for LMFBR

    International Nuclear Information System (INIS)

    Chen Daolong

    1996-07-01

    The constructions and performances of lots of newly developed intelligent type sodium instrumentations are described. The graduation characteristic equations for corresponding transducer using the medium temperature as the parameter are given. These intelligent type sodium instrumentations are possessed of good linearity. The accurate measurement data of sodium process parameters (flowrate, pressure and level) can be obtained by means of their on-line compensation function of the temperature effect. Moreover, these intelligent type sodium instrumentations are possessed of the self-inspection, the electric shutoff protection, the setting of full-scale, the setting of alarm limits (two upper limits and two lower limits alarms), the thermocouple breaking alarm, mutual isolative the 0∼10 V direct-current analogue output and the CENTRONICS standard digital output, and the alarm relay contact output. Theses intelligent type sodium instrumentations are suitable particularly for the instrument, control and protective systems of LMFBR by means of these excellent functions based on microprocessor. The basic errors of the intelligent type sodium flowmeter, immersed sodium flowmeter, sodium manometer and sodium level gauge are +-2%, +-2.3%, +-0.3% and +-1.9% of measuring ranges respectively. (9 figs.)

  6. Functional Analysis of P4-ATPases

    DEFF Research Database (Denmark)

    Theorin, Lisa

    Across membranes of the late secretory pathway in eukaryotic cells an asymmetric lipid distribution is maintained, with the lipids phosphatidylserine and phosphatidylethanolamine restricted to the cytoplasmic leaflet of the membrane. In recent years a subgroup of P-type ATPases, P4-ATPases, has...... and mammalian P4-ATPases have been studied extensively and the physiological function is mostly known, while the exact biochemistry and specific activity is mostly unknown. Even though the plant Arabidopsis thaliana has 12 P4-ATPases, not much is known about their function. In this study, the biochemical...... properties, with a focus on the lipid requirements, of the Aminophospholipid ATPase 2 (ALA2), a P4-ATPase from A. thaliana, were characterized. Heterologous expression of ALA2 together with its subunit, the Cdc50 homolog ALA Interacting Subunit 5 (ALIS5), in the yeast Saccharomyces cerevisiae allowed...

  7. Decoding P4-ATPase substrate interactions.

    Science.gov (United States)

    Roland, Bartholomew P; Graham, Todd R

    Cellular membranes display a diversity of functions that are conferred by the unique composition and organization of their proteins and lipids. One important aspect of lipid organization is the asymmetric distribution of phospholipids (PLs) across the plasma membrane. The unequal distribution of key PLs between the cytofacial and exofacial leaflets of the bilayer creates physical surface tension that can be used to bend the membrane; and like Ca 2+ , a chemical gradient that can be used to transduce biochemical signals. PL flippases in the type IV P-type ATPase (P4-ATPase) family are the principle transporters used to set and repair this PL gradient and the asymmetric organization of these membranes are encoded by the substrate specificity of these enzymes. Thus, understanding the mechanisms of P4-ATPase substrate specificity will help reveal their role in membrane organization and cell biology. Further, decoding the structural determinants of substrate specificity provides investigators the opportunity to mutationally tune this specificity to explore the role of particular PL substrates in P4-ATPase cellular functions. This work reviews the role of P4-ATPases in membrane biology, presents our current understanding of P4-ATPase substrate specificity, and discusses how these fundamental aspects of P4-ATPase enzymology may be used to enhance our knowledge of cellular membrane biology.

  8. German position paper on structural analysis for LMFBR applications

    International Nuclear Information System (INIS)

    Angerbauer, A.; Link, F.

    1983-01-01

    During the design period of the German LMFBR, the SNR-300, extensive work had been done in the field of elastic and inelastic analysis. Furthermore, special design rules have been developed. A review of these activities and their state-of-the art is outlined in this paper

  9. Technical considerations relative to removal of sodium from LMFBR components

    International Nuclear Information System (INIS)

    McDonald, J.S.; Asquith, J.G.

    1975-01-01

    Reviewed in this paper are technical considerations which are of importance in choosing between an alcohol process and a moist nitrogen process for the removal of sodium from LMFBR components. Results observed in laboratory tests and in the cleaning of large scale components (e.g. a 28 MWt Modular Steam Generator Test Unit) are presented and discussed. (author)

  10. Studies of LMFBR: method of analysis and some results

    International Nuclear Information System (INIS)

    Ishiguro, Y.; Dias, A.F.; Nascimento, J.A. do.

    1983-01-01

    Some results of recent studies of LMFBR characteristics are summarized. A two-dimensional model of the LMFBR is taken from a publication and used as the base model for the analysis. Axial structures are added to the base model and a three-dimensional (Δ - Z) calculation has been done. Two dimensional (Δ and RZ) calculations are compared with the three-dimensional and published results. The eigenvalue, flux and power distributions, breeding characteristics, control rod worth, sodium-void and Doppler reactivities are analysed. Calculations are done by CITATION using six-group cross sections collapsed regionwise by EXPANDA in one-dimensional geometries from the 70-group JFS library. Burnup calculations of a simplified thorium-cycle LMFBR have also been done in the RZ geometry. Principal results of the studies are: (1) the JFS library appears adequate for predicting overall characteristics of an LMFBR, (2) the sodium void reactivity is negative within - 25 cm from the outer boundary of the core, (3) the halflife of Pa-233 must be considered explicitly in burnup analyses, and (4) two-dimensional (RZ and Δ) calculations can be used iteratively to analyze three-dimensional reactor systems. (Author) [pt

  11. Assessment of accident energetics in LMFBR core-disruptive accidents

    International Nuclear Information System (INIS)

    Fauske, H.K.

    1977-01-01

    An assessment of accident energetics in LMFBR core-disruptive accidents is given with emphasis on the generic issues of energetic recriticality and energetic fuel-coolant interaction events. Application of a few general behavior principles to the oxide-fueled system suggests that such events are highly unlikely following a postulated core meltdown event

  12. Refractory metal carbide coatings for LMFBR applications: a systems approach

    International Nuclear Information System (INIS)

    Gotschall, H.L.; Ople, F.S.; Riccardella, P.C.

    1975-01-01

    The selection, testing and improvement of high density, tightly bonded plasma and detonation gun coatings designed to meet LMFBR core component criteria are described. The process descriptions include a review of the important developments in substrate surface preparation which were required to ensure strong bonding and to minimize interface contamination. Coating finishing techniques which were developed to optimize friction behavior are also described

  13. Advanced methods for fabrication of PHWR and LMFBR fuels

    International Nuclear Information System (INIS)

    Ganguly, C.

    1988-01-01

    For self-reliance in nuclear power, the Department of Atomic Energy (DAE), India is pursuing two specific reactor systems, namely the pressurised heavy water reactors (PHWR) and the liquid metal cooled fast breeder reactors (LMFBR). The reference fuel for PHWR is zircaloy-4 clad high density (≤ 96 per cent T.D.) natural UO 2 pellet-pins. The advanced PHWR fuels are UO 2 -PuO 2 (≤ 2 per cent), ThO 2 -PuO 2 (≤ 4 per cent) and ThO 2 -U 233 O 2 (≤ 2 per cent). Similarly, low density (≤ 85 per cent T.D.) (UPu)O 2 pellets clad in SS 316 or D9 is the reference fuel for the first generation of prototype and commercial LMFBRs all over the world. However, (UPu)C and (UPu)N are considered as advanced fuels for LMFBRs mainly because of their shorter doubling time. The conventional method of fabrication of both high and low density oxide, carbide and nitride fuel pellets starting from UO 2 , PuO 2 and ThO 2 powders is 'powder metallurgy (P/M)'. The P/M route has, however, the disadvantage of generation and handling of fine powder particles of the fuel and the associated problem of 'radiotoxic dust hazard'. The present paper summarises the state-of-the-art of advanced methods of fabrication of oxide, carbide and nitride fuels and highlights the author's experience on sol-gel-microsphere-pelletisation (SGMP) route for preparation of these materials. The SGMP process uses sol gel derived, dust-free and free-flowing microspheres of oxides, carbide or nitride for direct pelletisation and sintering. Fuel pellets of both low and high density, excellent microhomogeneity and controlled 'open' or 'closed' porosity could be fabricated via the SGMP route. (author). 5 tables, 14 figs., 15 refs

  14. Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Progress report, September 1, 1976--November 30, 1976

    Energy Technology Data Exchange (ETDEWEB)

    Todreas, N.E.; Golay, M.W.; Wolf, L.

    1976-01-01

    Information is presented concerning bundle geometry with wrapped and bare rods, subchannel geometry with bare rods, LMFBR outlet plenum flow mixing, and theoretical determination of local temperature fields in LMFBR fuel rod bundles.

  15. Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Progress report, March 1, 1977--May 31, 1977

    International Nuclear Information System (INIS)

    Todreas, N.E.; Golay, M.W.; Wolf, L.

    1977-01-01

    Progress is summarized in the following tasks: (1) bundle flow studies (wrapped and bare rods); (2) subchannel flow studies (bare rods); (3) LMFBR outlet plenum flow mixing; and (4) theoretical determination of local temperature fields in LMFBR fuel rod bundles

  16. A note on p-groups of order ≤ p4p4p4

    Indian Academy of Sciences (India)

    Abstract. In [1], we defined c(G), q(G) and p(G). In this paper we will show that if. G is a p-group, where p is an odd prime and |G| ≤ p4, then c(G) = q(G) = p(G). However, the question of whether or not there is a p-group G with strict inequality c(G) = q(G) < p(G) is still open. Keywords. Quasi-permutation representations ...

  17. On LMFBR corrosion. Part II: Consideration of the in-reactor fuel-cladding system

    International Nuclear Information System (INIS)

    Bradbury, M.H.; Pickering, S.; Walker, C.T.; Whitlow, W.H.

    1976-05-01

    The scientific and technological aspects of LMFBR cladding corrosion are discussed in detail. Emphasis is placed on the influence of the irradiation environment and the effect of fuel and filler-gas impurities on the corrosion process. These studies are complemented by a concise review of out-of-pile simulation experiments that endeavour to clarify the role of the aggressive fission products cesium, tellurium and iodine. The principal models for cladding corrosion are presented and critically assessed. Areas of uncertainty are exposed and some pertinent experiments are suggested. Consideration is also given to some new observations regarding the role of stress in fuel-cladding reactions and the formation of ferrite in the corrosion zone of the cladding during irradiation. Finally, two technological solutions to the problem of cladding corrosion are proposed. These are based on the use of an oxygen buffer in the fuel and the application of a protective coating to the inner surface of the cladding

  18. An experimental study on sodium-water reaction in the double pool LMFBR, (4)

    International Nuclear Information System (INIS)

    Kumagai, Hiromichi; Yoshida, Kazuo; Uotani, Masaki; Akimoto, Tokuzo

    1989-01-01

    Double Pool type LMFBR set the rectangular cross-sectional steam generator (SGs) inside a secondary vessel. The initial spike pressure rise caused by large sodium-water reaction in SGs might be radiated into a large sodium pool in the secondary vessel. Therefore basic experiments on pressure wave propagation were carried out by generating pressure wave in water by mean of a set of drop hummer and piston. But the experimental apparatus in water was not convenience to simulate the structure near the bottom end of the SGs shell. In this reports, experiments were carried out by generating pulse sound pressure in air, and compared with the results pressure waves in water. (author)

  19. LMFBR Blanket Physics Project progress report No. 2

    International Nuclear Information System (INIS)

    Forbes, I.A.; Driscoll, M.J.; Rasmussen, N.C.; Lanning, D.D.; Kaplan, I.

    1971-01-01

    This is the second annual report of an experimental program for the investigation of the neutronics of benchmark mock-ups of LMFBR blankets. Work was devoted primarily to measurements on Blanket Mock-Up No. 2, a simulation of a typical large LMFBR radial blanket and its steel reflector. Activation traverses and neutron spectra were measured in the blanket; calculations of activities and spectra were made for comparison with the measured data. The heterogeneous self-shielding effect for 238 U capture was found to be the most important factor affecting the comparison. Optimization and economic studies were made which indicate that the use of a high-albedo reflector material such as BeO or graphite may improve blanket neutronics and economics

  20. Development of acidic processes for decontaminating LMFBR components

    International Nuclear Information System (INIS)

    Hill, E.F.; Colburn, R.P.; Lutton, J.M.; Maffei, H.P.

    1978-01-01

    The objective of the DOE decontamination program is to develop a well characterized chemical decontamination process for application to LMFBR primary system components that subsequently permits contact maintenance and allows requalification of the components for reuse in reactors. The paper describes the subtasks of deposit characterization, development of requalification and process acceptance criteria, development of process evaluation techniques and studies which led to a new acidic process for decontaminating 304 stainless steel hot leg components

  1. Thermal analysis methods for LMFBR wire wrapped bundles

    International Nuclear Information System (INIS)

    Todreas, N.E.

    1976-11-01

    A note is presented which was written to stimulate an awareness and discussion of the fundamental differences in the formulation of certain existing analysis codes for LMFBR wire wrap bundles. The contention of the note is that for those array types where data exists (one wire per pin, equal start angles), the ENERGY method results for coolant temperature under forced convection conditions provide benchmarks of reliability equal to the results of codes COBRA and TH1-3D

  2. Large pool LMFBR design. Final report. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Wett, J. F.; Churchill, J. R.

    1979-03-01

    The design effort reported is an extension on past design effort and continuous concentration on those parts of the nuclear island unique to a commercial size pool type LMFBR. In particular, the work covers the reactor vessel, deck, rotating plugs, upper and lower internals, internal plenum separator system, IHX, pumps, cold traps, intermediate system layout, containment/confinement system, plot plan, and residual heat removal systems. Preliminary thermal, hydraulic, stress, and system analyses are also presented.

  3. Shielding design method for LMFBR validation on the Phenix factor

    International Nuclear Information System (INIS)

    Cabrillat, J.C.; Crouzet, J.; Misrakis, J.; Salvatores, M.; Rado, V.; Palmiotti, G.

    1983-05-01

    Shielding design methods, developed at CEA for shielding calculations find a global validation by the means of Phenix power reactor (250 MWe) measurements. Particularly, the secondary sodium activation of pool type LMFBR such as Super Phenix (1200 MWe) which is subject to strict safety limitation is well calculated by the adapted scheme, i.e. a two dimension transport calculation of shielding coupled to a Monte-Carlo calculation of secondary sodium activation

  4. A new approach to the design of LMFBR liners

    International Nuclear Information System (INIS)

    Polentz, L.M.

    1980-01-01

    An advance in the state-of-the-art of LMFBR liners which permits notable savings in construction costs without any sacrifice of safety is described. The application of the new design concept to the rework of the upper reactor vault liner of the FFTF is discussed. Factors which affect the application of the new design approach to other LMFBRs are delineated and discussed. (author)

  5. Structural analysis for elevated temperature design of the LMFBR

    International Nuclear Information System (INIS)

    Griffin, D.S.

    1976-02-01

    In the structural design of LMFBR components for elevated temperature service it is necessary to take account of the time-dependent, creep behavior of materials. The accommodation of creep to assure design reliability has required (1) development of new design limits and criteria, (2) development of more detailed representations of material behavior, and (3) application of the most advanced analysis techniques. These developments are summarized and examples are given to illustrate the current state of technology in elevated temperature design

  6. Future development LMFBR-steam generators SNR2

    International Nuclear Information System (INIS)

    Essebaggers, J.; Pors, J.G.

    1975-01-01

    The development work for steam generators for large LMFBR plants by Neratoom will be reviewed consisting of: 1. Development engineering information. 2. Concept select studies followed by conceptual designs of selected models. 3. Development manufacturing techniques. 4. Detail design of a prototype unit. 5. Testing of sub-constructions for prototype steam generators. In this presentation item 1 and 2 above will be high lighted, identifying the development work for the SNR-2 steam generators on short term basis. (author)

  7. Biological behavior of mixed LMFBR-fuel-sodium aerosols

    International Nuclear Information System (INIS)

    Mahlum, D.D.; Hackett, P.L.; Hess, J.O.; Allen, M.D.

    1979-01-01

    Immediately after exposure of rats to mixed aerosols of sodium-LMFBR fuel, about 80 to 90% of the body burden of 239 Pu is in the gastrointestinal tract; 1.5 to 4% is in the lungs. With fuel-only aerosols, less of the body burden was in the GI tract and more in the lung and the head. Blood and urine values suggest an increased absorption of 239 Pu from sodium-fuel than from fuel-only aerosols

  8. Compendium of computer codes for the safety analysis of LMFBR's

    International Nuclear Information System (INIS)

    1975-06-01

    A high level of mathematical sophistication is required in the safety analysis of LMFBR's to adequately meet the demands for realism and confidence in all areas of accident consequence evaluation. The numerical solution procedures associated with these analyses are generally so complex and time consuming as to necessitate their programming into computer codes. These computer codes have become extremely powerful tools for safety analysis, combining unique advantages in accuracy, speed and cost. The number, diversity and complexity of LMFBR safety codes in the U. S. has grown rapidly in recent years. It is estimated that over 100 such codes exist in various stages of development throughout the country. It is inevitable that such a large assortment of codes will require rigorous cataloguing and abstracting to aid individuals in identifying what is available. It is the purpose of this compendium to provide such a service through the compilation of code summaries which describe and clarify the status of domestic LMFBR safety codes. (U.S.)

  9. Performance of LMFBR fuel pins with (Pu,Th)O/sub 2-x/ and UO2

    International Nuclear Information System (INIS)

    Lawrence, L.A.

    1983-09-01

    The irradiation performance of (Pu,Th)O/sub 2-x/ and UO 2 fueled pins for breeder reactor application were compared to the extensive performance data base for the (U,Pu)O/sub 2-x/ fuel system. Th-Pu and 238 U- 233 U based fuel systems were candidate fuel fertile/fissile isotopic combinations for development of alternatives to the current LMFBR fuel cycle. Initial screening tests were conducted in the EBR-II to obtain comparative performance data because of the limited experience with these fuel systems. In some cases, 235 U was used as a substitute for 233 U because of the difficulties in fabrication of available 233 U due to its high gamma ray emission rate

  10. X-ray M4,5 Resonant Raman Scattering from La metal with final 4p hole: Calculations with 4p-4d-4f configuration interaction in the final state and comparison with the experiment

    International Nuclear Information System (INIS)

    Taguchi, M.; Braicovich, L.; Tagliaferri, A.; Dallera, C.; Giarda, K.; Ghiringhelli, G.; Brookes, N.B.; Borgatti, F.

    2001-03-01

    We consider the X-Ray Resonant Raman Scattering (RRS) in La in the whole M 4,5 region ending with a state with a 4p hole, along the sequence 3d 10 4f 0 →3d 9 4f 1 →3d 10 4p 5 4f 1 . The final state configuration mixes with that with two 4d holes i.e. 3d 10 4d 8 4f n+2 having almost the same energy. Thus RRS must be described by introducing final state Configuration Interaction (CI) between states with one 4p hole and with two 4d holes. This approach allows detailed experimental data on La-metal to be interpreted on the basis of a purely ionic approach. It is shown that the inclusion of CI is crucial and has very clear effects. The calculations with the Kramers-Heisenberg formula describe all measured spectral features appearing in the strict Raman regime i.e. dispersing with the incident photon energy. In the experiment also a nondispersive component is present when the excitation energy is greater than about 2 eV above the M 5 peak. The shape and position of this component is well accounted for by a model based on all possible partitions of the excitation energy between localised and extended states. However, the intensity of the nondispersive component is greater in the measurements, suggesting a rearrangement in the intermediate excited state. The comparison of ionic calculations with the metal measurements is legitimate, as shown by the comparison between the measurements on La-metal and on LaF 3 with M 5 excitation, giving the same spectrum within the experimental accuracy. Moreover, the experiment shows that the final lifetime broadening is much greater in the final states corresponding to lower outgoing photon energies than in the states corresponding to higher outgoing photon energies. (author)

  11. Sodium water reaction R and D for French LMFBR

    International Nuclear Information System (INIS)

    Cambillard, E.; Finck, P.; Lapicore, A.; Simeon, C.

    1985-01-01

    This paper presents the research and development which is underway for the French LMFBR steam generator safety study. The program comprises three major areas: (1) the analysis of realistic leaks, which includes the leak evolution and its consequences; (2) the response time of leak detection systems compared to leak propagation phenomena; and (3) the guillotine rupture (DBA) studies relative to source term evaluation by experimental/calculational approach and mechanical calculations. This program has provided information for the demonstrations of the steam generator safety in respect to a sodium-water reaction

  12. LMFBR steam generator leak detection development in the United States

    International Nuclear Information System (INIS)

    Magee, P.M.; Gerrels, E.E.; Greene, D.A.; McKee, J.

    1978-01-01

    Leak detection for Liquid Metal Fast Breeder Reactor steam generators is an important economic factor in the shutdown, repair and restart of a plant. Development of leak detection systems in the U.S. has concentrated on four areas: (1) chemical (H 2 and O 2 ) leak detection meters; (2) acoustic leak detection/location techniques; (3) investigation of leak behavior (enlargement, damage effects, plugging and unplugging); and (4) data management for plant operations. This paper discusses the status, design aspects, and applications of leak detection technology for LMFBR plants. (author)

  13. LMFBR fuel cycle studies progress report, August 1972, No. 42

    International Nuclear Information System (INIS)

    Unger, W.E.; Blanco, R.E.; Crouse, D.J.; Irvine, A.R.; Watson, C.D.

    1972-10-01

    This report continues a series outlining progress in the development of methods for reprocessing of LMFBR fuels. Development work is reported on problems of irradiated fuel transport to the processing facility, the dissolution of the fuel and the chemical recovery of PuO 2 --UO 2 values, the containment of volatile fission products, product purification, conversion of fuel processing plant product nitrate solutions to solids suitable for shipping and for subsequent fuel fabrication. Pertinent experimental results are presented for the information of those immediately concerned with the field. Detailed description of experimental work and data are included in the topical reports and in the Chemical Technology Division Annual Reports

  14. Immersed acoustical transducers and their potential uses in LMFBR

    International Nuclear Information System (INIS)

    Argous, J.P.; Brunet, M.; Baron, J.; Lhuillier, C.; Segui, J.L.

    1980-04-01

    Six years satisfactory operation in PHENIX has proved the reliability and effectivness of under-sodium viewing (VISUS) and Acoustic Detection. This fact has been strong incentive to maintain, on the future LMFBR the visus as well as the Acoustic Detection functions. These two functions are performed on SUPER PHENIX, by two sets of distinct systems using the well-known solution. Taking into account of recent improvements in sodium immersible acoustic transducers technology, CEA decided to undertake the development of a multi-functions instrument. This paper gives an outline of this new concept, which should be able to reduce the cost and the complexity of core instrumentation

  15. Assessment of transport effects in LMFBR safety neutronics

    International Nuclear Information System (INIS)

    Cahalan, J.E.; Ott, K.O.; Ferguson, D.R.

    1976-01-01

    A qualitative and quantitative assessment of the significance of neutron transport effects in LMFBR core disruptive accident analysis is presented. Material relocations which might cause important neutron transport behavior are identified. A quantitative measure of the error in the neutron flux is obtained from a consistent numerical comparison of transport and diffusion theory eigenvalue solutions for models of disrupted cores. A numerical technique for the prediction of transport eigenvalues and eigenvectors is formulated and applied. The technique is based on a modified diffusion theory which is fully capable of reproducing transport theory solutions

  16. Proposal for computer investigation of LMFBR core meltdown accidents

    International Nuclear Information System (INIS)

    Boudreau, J.E.; Harlow, F.H.; Reed, W.H.; Barnes, J.F.

    1974-01-01

    The environmental consequences of an LMFBR accident involving breach of containment are so severe that such accidents must not be allowed to happen. Present methods for analyzing hypothetical core disruptive accidents like a loss of flow with failure to scram cannot show conclusively that such accidents do not lead to a rupture of the pressure vessel. A major deficiency of present methods is their inability to follow large motions of a molten LMFBR core. Such motions may lead to a secondary supercritical configuration with a subsequent energy release that is sufficient to rupture the pressure vessel. The Los Alamos Scientific Laboratory proposes to develop a computer program for describing the dynamics of hypothetical accidents. This computer program will utilize implicit Eulerian fluid dynamics methods coupled with a time-dependent transport theory description of the neutronic behavior. This program will be capable of following core motions until a stable coolable configuration is reached. Survey calculations of reactor accidents with a variety of initiating events will be performed for reactors under current design to assess the safety of such reactors

  17. Analytical approach for confirming the achievement of LMFBR reliability goals

    International Nuclear Information System (INIS)

    Ingram, G.E.; Elerath, J.G.; Wood, A.P.

    1981-01-01

    The approach, recommended by GE-ARSD, for confirming the achievement of LMFBR reliability goals relies upon a comprehensive understanding of the physical and operational characteristics of the system and the environments to which the system will be subjected during its operational life. This kind of understanding is required for an approach based on system hardware testing or analyses, as recommended in this report. However, for a system as complex and expensive as the LMFBR, an approach which relies primarily on system hardware testing would be prohibitive both in cost and time to obtain the required system reliability test information. By using an analytical approach, results of tests (reliability and functional) at a low level within the specific system of interest, as well as results from other similar systems can be used to form the data base for confirming the achievement of the system reliability goals. This data, along with information relating to the design characteristics and operating environments of the specific system, will be used in the assessment of the system's reliability

  18. Seismic behaviour of LMFBR reactor cores. The SYMPHONY program

    International Nuclear Information System (INIS)

    Broc, Daniel

    2001-01-01

    As part of a comprehensive program on the seismic behaviour of the LMFBR reactor cores, the SYMPHONY experimental program, performed at the CEA Saclay, is carried out from 1993 up to now. LMFBR reactor cores are composed of fuel assemblies and neutronic shields, immersed in sodium (the primary coolant) or water (for the experimental tests). The main objective of the seismic studies is to evaluate the assembly motions, with consequences on the reactivity and the control rod insertability, and to verify the structural integrity of the assemblies under the impact forces. The experimental program has reached its objectives. Tests have been performed in a satisfying way. Instrumentation allowed to collect displacements, accelerations, and shock forces. All the results constitute a comprehensive base of valuable and reliable data. The interpretation of the tests is based on beam models, taking into account the Fluid Structure Interaction, and the shocks between the assemblies. Theoretical results are in a quite good agreement with the experimental ones. The interpretation of the hexagonal tests in water pointed out very strong coupling between the assemblies and lead to the development of a specific Fluid Structure Interaction, taking into account not only inertial effects, but dissipative effects also. (author)

  19. Transient analysis of LMFBR reinforced/prestressed concrete containment

    International Nuclear Information System (INIS)

    Marchertas, A.H.; Belytschko, T.B.; Bazant, Z.P.

    1979-01-01

    The use of prestressed concrete reactor vessels (PCRVs) for LMFBR containment creates a need for analytical methods for treating the transient response of such structures, for LMFBR containments must be capable of sustaining the dynamic effects which arise in a hypothetical core disruptive accident (HCDA). These analyses require several unique features: a model of concrete which includes tensile cracking, a methodology for representing the prestressing tendons and for simulating the prestressing operation, and an efficient computational tool for treating the transient response. Furthermore, for the sake of convenience, all of these features should be available in a single computer code. For the purpose of treating the transient response, a finite element program with explicit time integration was chosen. The use of explicit time integration has the advantage that it can easily treat the complicated constitutive model which arises from the considerations of concrete cracking and it can handle the slip between reinforcing tendons and the concrete through the use of the well known sliding interface options. However, explicit time integration programs are usually not well suited to the simulation of static processes such as prestressing. Nevertheless, explicit time integration programs can handle static processes through the introduction of damping by what is known as a dynamic relaxation procedure. For this reason, the dynamic relaxation procedure was refined through the introduction of lumped mass, viscous damping. This provision made the prestressing operation of the concrete structures by means of the explicit formulation rather convenient. (orig.)

  20. State of the art review of degradation processes in LMFBR materials. Volume II. Corrosion behavior

    International Nuclear Information System (INIS)

    Dillon, R.D.

    1975-01-01

    Degradation of materials exposed to Na in LMFBR service is reviewed. The degradation processes are discussed in sections on corrosion and mass transfer, erosion, wear and self welding, sodium--water reactions, and external corrosion. (JRD)

  1. Study on the seismic response of reactor vessel of pool type LMFBR including fluid-structure interaction

    International Nuclear Information System (INIS)

    Tanimoto, K.; Ito, T.; Fujita, K.; Kurihara, C.; Sawada, Y.; Sakurai, A.

    1988-01-01

    The paper presents the seismic response of reactor vessel of pool type LMFBR with fluid-structure interaction. The reactor vessel has bottom support arrangement, the same core support system as Super-Phenix in France. Due to the bottom support arrangement, the level of core support is lower than that of the side support arrangement. So, in this reactor vessel, the displacement of the core top tends to increase because of the core's rocking. In this study, we investigated the vibration and seismic response characteristics of the reactor vessel. Therefore, the seismic experiments were carried out using one-eighth scale model and the seismic response including FSI and sloshing were investigated. From this study, the effect of liquid on the vibration characteristics and the seismic response characteristics of reactor vessel were clarified and sloshing characteristics were also clarified. It was confirmed that FEM analysis with FSI can reproduce the seismic behavior of the reactor vessel and is applicable to seismic design of the pool type LMFBR with bottom support arrangement. (author). 5 refs, 14 figs, 2 tabs

  2. Analysis of a postulated accident scenario involving loss of forced flow in a LMFBR

    International Nuclear Information System (INIS)

    Moreira, M.L.

    1985-01-01

    A model to analyse a postulated accident scenario involving loss of forced flow in the reactor vessel of a LMFBR is used. Five phases of the accident are analysed: Natural Circulation, Subcooled Boiling, Nucleate Boiling, Core Dryout and Cladding melt. The heat conduction in the fuel cladding, coolant and lower and upper plenum are calculated by a lump-parameter model. Physical data of a prototype LMFBR reactor were used for the calculation. (author)

  3. Thermal experiments with LMFBR subassembly models in sodium flow

    International Nuclear Information System (INIS)

    Moeller, R.; Tschoeke, H.

    1982-01-01

    Within the framework of the Fast Breeder Project research work has been undertaken at the Karlsruhe Nuclear Research Center on the thermal and fluid dynamics of nominal and distorted core subassemblies. In 19-rod bundle models (P/D=1.30, W/R=1.38) three-dimensional temperature distributions were measured in the cladding tubes exposed to sodium flow. Results of measurements of the azimuthal temperature profiles of rotated rods in the duct wall zone are indicated for different operating conditions 80 2 , evenly distributed load and oblique load; different axial positions of the spacer grids; and different positions of one bowed rod

  4. Program for the development of design data: LMFBR steam generator materials

    Energy Technology Data Exchange (ETDEWEB)

    None

    1976-01-01

    Progress in fiscal year 1976 is reported for two tasks in the LMFBR steam generator materials development program. The primary objective of Task 18 is characterization of materials, mainly 2-1/4 Cr-1 Mo and austenitic stainless steels, to assure that satisfactory materials compatibility is achieved with LMFBR steam generator environments. Studies described include: the kinetics and magnitude of decarburization of 2-1/4 Cr-1 Mo in high temperature liquid sodium; decarburization effects on mechanical properties; stress corrosion susceptibility of 2-1/4 Cr-1 Mo in water/steam environments of LMFBR steam generators; and stainless steel mechanical properties within a carburizing sodium environment at high temperatures. In addition, two activities are in progress that directly support LMFBR steam generator design and fabrication. Under Subtask E, General Electric heads the working committee on steam generator materials for the Nuclear Systems Materials Handbook. Subtask F, an experimental effort, is investigating thermal degradation effects produced by particulate deposition (in sodium) on heat transfer surfaces. The Steam Generator Materials Qualification Task (Task 10-G) was initiated in support of the development of materials and processes used in Clinch River Breeder Reactor steam generators. The topics discussed are: LMFBR steam generator tubing; LMFBR steam generator tubesheet forgings (characterization of VAR/ESR melted 2-1/4 Cr-1 Mo); friction, wear and self-welding; nondestructive examination development; water chemistry studies; and transition joint development.

  5. Natural circulation in simulated LMFBR fuel assemblies

    International Nuclear Information System (INIS)

    Levin, A.E.; Carbajo, J.J.; Lloyd, D.B.; Montgomery, B.H.; Rose, S.D.; Wantland, J.L.

    1985-01-01

    Natural circulation experiments have been performed using simulated liquid metal fast breeder reactor fuel assemblies in the Thermal-Hydraulic Out-of-Reactor Safety (THORS) facility, an engineering-scale sodium loop. Objective of these tests has been to provide experimental data under conditions that might be encountered during a partial or total loss of the shutdown heat removal system (SHRS) in a reactor. The experiments have included single- and two-phase tests under quasi-steady and transient conditions, at both nominal and non-nominal system conditions. Results from these test indicate that the potential for reactor damage during degraded SHRS operation is extremely slight, and that natural circulation can be a major contributor to safe operation of the system in both single- and two-phase flow during such operation

  6. Thermalhydraulic characteristics in LMFBR hot plenum

    International Nuclear Information System (INIS)

    Tanaka, N.; Moriya, S.; Wada, A.

    1983-01-01

    The most important problem in the thermalhydraulic designs of the pool-type FBR is to estimate the thermal conditions affecting the vessel and/or internal structures during both steady and transient operations. The severity of these conditions in the Japanese pool-type reactor which will be reinforced and equipped with special devices for aseismic demands are apt to be much greater than other countries. Water tests and thermalhydraulic analyses have been performed to study such conditions. The main purpose of this study is to estimate the effects of the elevations of UIS (Upper Internal Structure) discharge and IHX (Intermediate Heat Exchanger) intakes of flow patterns, free surface disturbance and thermal-stratification in hot plenum. From the results of the experiments, suitable elevations could be recommended by comparing some thermalhydraulic characteristics. The calculation agreed well with the experimental results on the steady-state flow patterns and thermal-transients except the thermal-stratification

  7. Blockages in LMFBR fuel assemblies: a review

    International Nuclear Information System (INIS)

    Han, J.T.; Fontana, M.H.

    1977-01-01

    Experimental and analytical investigations performed in the United States, Germany, Great Britain, and Japan on the effects of partial flow blockages in liquid-metal fast breeder reactor fuel assemblies are reviewed and the results presented. Generalized models are developed from experimental data obtained for blockages of various sizes, shapes, and porosity, with and without pins, utilizing water and sodium as the coolant. Generally, the recirculating flow in the wake behind a blockage is a relatively effective heat transfer mechanism. Experiments where sodium boiling was made to occur behind the blockages indicate that boiling is stable for the configurations tested; these results are predicted by analytical models. Blockages at the inlet of fuel assemblies tend to have insignificant effects in the fuel assembly unless flow is reduced grossly and therefore would be detectable. Blockages in the heat generating zone have to be quite large to cause sodium boiling under normal reactor operating conditions

  8. Blockages in LMFBR fuel assemblies: a review

    Energy Technology Data Exchange (ETDEWEB)

    Han, J T; Fontana, M H

    1977-01-01

    Experimental and analytical investigations performed in the United States, Germany, Great Britain, and Japan on the effects of partial flow blockages in liquid-metal fast breeder reactor fuel assemblies are reviewed and the results presented. Generalized models are developed from experimental data obtained for blockages of various sizes, shapes, and porosity, with and without pins, utilizing water and sodium as the coolant. Generally, the recirculating flow in the wake behind a blockage is a relatively effective heat transfer mechanism. Experiments where sodium boiling was made to occur behind the blockages indicate that boiling is stable for the configurations tested; these results are predicted by analytical models. Blockages at the inlet of fuel assemblies tend to have insignificant effects in the fuel assembly unless flow is reduced grossly and therefore would be detectable. Blockages in the heat generating zone have to be quite large to cause sodium boiling under normal reactor operating conditions.

  9. Gravitational agglomeration of post-HCDA LMFBR aerosols: nonspherical particles

    International Nuclear Information System (INIS)

    Tuttle, R.F.; Loyalka, S.K.

    1982-12-01

    Aerosol behavior analysis computer programs have shown that temporal aerosol size distributions in nuclear reactor containments are sensitive to shape factors. This research investigates shape factors by a detailed theoretical analysis of hydrodynamic interactions between a nonspherical particle and a spherical particle undergoing gravitational collisions in an LMFBR environment. First, basic definitions and expressions for settling speeds and collisional efficiencies of nonspherical particles are developed. These are then related to corresponding quantities for spherical particles through shape factors. Using volume equivalent diameter as the defining length in the gravitational collision kernel, the aerodynamic shape factor, the density correction factor, and the gravitational collision shape factor, are introduced to describe the collision kernel for collisions between aerosol agglomerates. The Navier-Stokes equation in oblate spheroidal coordinates is solved to model a nonspherical particle and then the dynamic equations for two particle motions are developed. A computer program (NGCEFF) is constructed, and the dynamical equations are solved by Gear's method

  10. Buoyancy effects on turbulent mixing in the LMFBR outlet plenum

    International Nuclear Information System (INIS)

    Chang, S.H.

    1983-01-01

    The effect of flow stratification is of particular concern during transient after scram in the outlet plenum of LMFBR. In this case, buoyancy effects on turbulent mixing are the importance to designers. An investigation has been made to identify the appropriate change in the available turbulence models which are necessary to include the effects of buoyancy on turbulence transport equations. The developed physical model of the buoyant turbulent flow are solved through SMAC method. Testing of the developed numerical model was undertaken and compared with experimental results. The results show that the buoyant turbulent effects account for the significant increase in the stability of the stratification, with a strong suppression of turbulence in the outlet plenum. (Author)

  11. Computational technique for estimating corrosion product release in an LMFBR

    International Nuclear Information System (INIS)

    Kuhn, W.L.

    1976-01-01

    A model is developed to predict the release of activated corrosion products in an LMFBR. Model parameters are obtained from literature correlations and from fitting the model to release rates observed in experimental sodium loops. The model is simplified to consider only two cases: release controlled by corrosion only or controlled by simultaneous corrosion and diffusion only. The release rates, radionuclide inventories, and resulting radiation fields near primary system components are predicted for the Fast Flux Test Facility as a function of operating temperature, oxygen concentration in the sodium, and time of operation. Saturation inventories are reported for 54 Mn, 60 Co, 58 Co, 51 Cr, and 59 Fe. The resulting radiation fields are due mainly to 54 Mn, and are found to reach the 5 R/hr range for operation at a core outlet temperature of 593 0 C

  12. Probabilistic assessment of critically flawed LMFBR PHTS piping elbows

    International Nuclear Information System (INIS)

    Balkey, K.R.; Wallace, I.T.; Vaurio, J.K.

    1982-01-01

    One of the important functions of the Primary Heat Transport System (PHTS) of a large Liquid Metal Fast Breeder Reactor (LMFBR) plant is to contain the circulating radioactive sodium in components and piping routed through inerted areas within the containment building. A significant possible failure mode of this vital system is the development of cracks in the piping components. This paper presents results from the probabilistic assessment of postulated flaws in the most-critical piping elbow of each piping leg. The criticality of calculated maximum sized flaws is assessed against an estimated material fracture toughness to determine safety factors and failure probability estimates using stress-strength interference theory. Subsequently, a different approach is also employed in which the randomness of the initial flaw size and loading are more-rigorously taken into account. This latter approach yields much smaller probability of failure values when compared to the stress-strength interference analysis results

  13. Neutron and gamma transport effects by heterogeneous core designs. [LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Lam, S.K.

    1977-01-01

    The use of diffusion theory for the prediction of power production near a reactor core-blanket interface and the assumption that gammas are absorbed in situ can lead to substantial errors. This is primarily due to the breakdown of Fick's law for neutron diffusion near the core-blanket boundary, and the gamma leakage from the core into the blanket. These considerations are more pronounced in a situation where a large number of internal blanket assemblies are present, such as in the large heterogeneous core designs. The power distribution is studied for both fission and gamma heating in a large heterogeneous LMFBR with 3 core zones separated by 2 internal blanket zones. Comparisons are made between diffusion and transport theory for neutronics calculations, and between in-situ absorption and rigorous transport theory calculation for gamma heating.

  14. CAT reconstruction and potting comparison of a LMFBR fuel bundle

    International Nuclear Information System (INIS)

    Betten, P.R.; Tow, D.M.

    1984-04-01

    A standard Liquid Metal Fast Breeder Reactor (LMFBR) subassembly used in the Experimental Breeder Reactor II (EBR-II) was investigated, by remote techniques, for fuel bundle distortion by both nondestructive and destructive methods, and the results from both methods were compared. The non-destructive method employed neutron tomography to reconstruct the locations of fuel elements through the use of a maximum entropy reconstruction algorithm known as MENT. The destructive method consisted of ''potting'' (a technique that embeds and permanently fixes the fuel elements in a solid matrix) the subassembly, and then cutting and polishing the individual sections. The comparison indicated that the tomography reconstruction provided good results in describing the bundle geometry and spacer-wire locations, with the overall resolution being on the order of a spacer-wire diameter. A dimensional consistency check indicated that the element and spacer-wire dimensions were accurately reproduced in the reconstruction

  15. A technique for computing bowing reactivity feedback in LMFBR's

    International Nuclear Information System (INIS)

    Finck, P.J.

    1987-01-01

    During normal or accidental transients occurring in a LMFBR core, the assemblies and their support structure are subjected to important thermal gradients which induce differential thermal expansions of the walls of the hexcans and differential displacement of the assembly support structure. These displacements, combined with the creep and swelling of structural materials, remain quite small, but the resulting reactivity changes constitute a significant component of the reactivity feedback coefficients used in safety analyses. It would be prohibitive to compute the reactivity changes due to all transients. Thus, the usual practice is to generate reactivity gradient tables. The purpose of the work presented here is twofold: develop and validate an efficient and accurate scheme for computing these reactivity tables; and to qualify this scheme

  16. Research and development of bellows for LMFBR in Japan

    International Nuclear Information System (INIS)

    Takahashi, Tadao; Mukai, Kazuo; Yamamoto, Ken.

    1979-11-01

    The bellows is employed as a useful mechanical element with its flexibility and imperviousness to liquid and gas in the system in which such chemically active substance as sodium is handled. Since the early time of development of Japanese LMFBR, bellows have been used e.g. for the shaft seal of small sodium valves. Bellows are employed in the fast experimental reactor JOYO which is now in operation and the fast prototype reactor MONJU whose design program is in final stage at the following parts: - control rod drive mechanism, - intermediate heat exchanger, - small valve, - mechanical penetration assembly of the containment boundary, - outer piping of the double-walled primary system (for JOYO only). In addition, the application of bellows as thermal expansion joint to the main piping system is under consideration for future FBRs. This paper outlines the research and development work on bellows for the FBR use in Japan. (author)

  17. Research and development of bellows for LMFBR in Japan

    International Nuclear Information System (INIS)

    Takahashi, T.; Mukai, K.; Yamamoto, K.

    1980-01-01

    Bellows are employed as useful mechanical elements with their flexibility and imperviousness to liquid and gas in the system in which such chemically active substances as sodium are handled. Since the early time of development of Japanese LMFBR, bellows have been used e.g. for the shaft seal of small sodium valves. Bellows are employed in the fast experimental reactor JOYO which is now in operation and the fast prototype reactor MONJU whose design program is in final stage at the following parts: control rod drive mechanism; intermediate heat exchanger; small valve; mechanical penetration assembly of the containment boundary; outer piping of the double-walled primary system (for JOYO only). In addition, the application of bellows as thermal expansion joint to the main piping system is under consideration for future FBRs. This paper outlines the research and development work on bellows for FBR use in Japan. (author)

  18. Fatigue of LMFBR piping due to flow stratification

    International Nuclear Information System (INIS)

    Woodward, W.S.

    1983-01-01

    Flow stratification due to reverse flow was simulated in a 1/5-scale water model of a LMFBR primary pipe loop. The stratified flow was observed to have a dynamic interface region which oscillated in a wave pattern. The behavior of the interface was characterized in terms of location, local temperature fluctuation and duration for various reverse flow conditions. A structural assessment was performed to determine the effects of stratified flow on the fatigue life of the pipe. Both the static and dynamic aspects of flow stratification were examined. The dynamic interface produces thermal striping on the inside of the pipe wall which is shown to have the most deleterious effect on the pipe wall and produce significant fatigue damage relative to a static interface

  19. MIT LMFBR blanket research project. Final summary report

    Energy Technology Data Exchange (ETDEWEB)

    Driscoll, M.J.

    1983-08-01

    This is a final summary report on an experimental and analytical program for the investigation of LMFBR blanket characteristics carried out at MIT in the period 1969 to 1983. During this span of time, work was carried out on a wide range of subtasks, ranging from neutronic and photonic measurements in mockups of blankets using the Blanket Test Facility at the MIT Research Reactor, to analytic/numerical investigations of blanket design and economics. The main function of this report is to serve as a resource document which will permit ready reference to the more detailed topical reports and theses issued over the years on the various aspects of project activities. In addition, one aspect of work completed during the final year of the project, on doubly-heterogeneous blanket configurations, is documented for the record.

  20. Specialists meeting on LMFBR flow induced vibrations. Summary report

    International Nuclear Information System (INIS)

    1977-12-01

    A Specialists' Meeting on LMFBR Flow-Induced Vibrations was held at ANL in the United States which was sponsored by the International Atomic Energy Agency (IAEA) on the recommendations of the International Working Group on Fast Reactors (IWGFR). It was attended by participants from France, the Federal Republic of Germany, Italy, Japan, Netherlands, the United Kingdom, the Union of Soviet Socialist Republics, the United States and the IAEA. The purpose of the meeting was to provide, for the first time, a common forum for the exchange of information on flow-induced vibration programs of the member countries. As this was a first meeting, information was sought in the broad areas of: 1. Design Criteria and Problem Areas in LMFBR Design; 2. Current Design Procedures; and 3. Ongoing Research. A session was devoted to each of the above topics wherein papers were presented and discussed followed by open discussions on the session topic. The objective of the open discussions was to identify, from a review of specific reactor designs, (a) flow induced vibration problem areas (expected and observed) and their potential for occurrence; (b) failure modes and associated design criteria; (c) specific components that are susceptible to flow induced vibration; and (d) probable excitation mechanisms. It was aimed to assess the current state-of-the-art in designing to avoid flow induced vibration with consideration of licensing requirements; to evaluate existing methods of analysis, testing, and surveillance, along with their limitations and to identify areas requiring research and review ongoing research programmes relative to these research needs

  1. LMFBR self-activated shutdown systems

    International Nuclear Information System (INIS)

    Sowa, E.S.; Barthold, W.P.; Eggen, D.T.; Huebotter, P.R.; Josephson, J.; Pizzica, P.A.; Turski, R.B.; van Erp, J.B.

    1976-01-01

    Self-actuated shutdown systems (SASSs), fully contained within the dimensions of a fuel subassembly and installed in the core in judiciously chosen locations, can provide an important additional safety feature for LMFBRs. If actuated by phenomena inherent to the system and its immediate environment, these systems can contribute considerably to the total reliability of the overall plant protection system, in particular as regards protection against human error. It was shown that this type of shutdown system is capable of inserting a substantial amount of negative reactivity into the core with a relatively small impact on plant performance. Furthermore, it was shown that a coolable geometry can be maintained in LMFBRs of current design for a wide spectrum of accident initiators, and for a range of response times and insertion rates which appear to be achievable within practical design limits. Experiments showed that Curie-point-operated devices have considerable promise for application in self-actuated shutdown systems, in particular as regards meeting the requirements of testability and resettability

  2. Review on Japanese activities in the field of maintenance and repair of LMFBR steam generators

    International Nuclear Information System (INIS)

    Tsuchiya, T.; Fukuda, T.; Sato, M.; Okabayashi, K.; Takahashi, T.

    2002-01-01

    Summary of Japanese activities on maintenance and repair of LMFBR steam generators (SG) is described in this paper. The concept (adoption of helical coil tube etc.) of MONJU SG was established in conceptional design started from 1968, and research and development (R and D) program was prepared. Parallel with basic studies such as material, welding, sodium water reaction and etc., overall verification tests using mock up SGs were conducted. As the first step, 1 Mw SG with two active helical tubes (and eight dummy tubes) was fabricated and operated, and many maintenance and repair experiences were accumulated through two small water leak troubles. Two 50Mw SGs, 1/5 scale of MONJU SG, were constructed and operated for long time. Post test examinations were carried out for No.1 50 Mw SG and feasibility of this type of SG was confirmed. In regard to maintenance and repair techniques, explosive and welding method for tube plugging and UT and ECT techniques for inspection of tube integrity are under development. Overall verification test for on-site and in-factory maintenance and repair techniques was conducted using No.2 50Mw SG evaporator and applicability of those techniques to real plant was evaluated. Many experiences were accumulated for removal and cleaning of sodium water reaction products after sodium water reaction in the cooling system and pressure relief system, using the Large Sodium Water Reaction Test Facility (SWAT-1 and 3). (author)

  3. Experimental study on fast neutron streaming through grid-plate shield of a LMFBR

    International Nuclear Information System (INIS)

    Oka, Yoshiaki; Wakabayashi, Hiroaki; An, Shigehiro; Suzuki, Ikunori.

    1976-01-01

    Neutron streaming through the holes penetrating the grid plate shield of a prototype LMFBR was experimentally examined. The mockups of the grid plate shield were made of iron and aluminum. Experiments were conducted at the vertical column of ''YAYOI'', the fast neutron source reactor of University of Tokyo. A He-3 spectrometer was employed in order to measure the transmitted neutron spectrum, while rhodium and indium threshold foils were for the integral flux above specific energies and their spatial distributions in the form of reaction rates. The streaming factor for usual small bended holes is 1.28+-0.04 as to the integral neutron flux above 0.1 MeV and 1.30+-0.12 as to the reaction rate of indium foil. Use were made of the one and two dimensional neutron transport code ANISN and TWOTRAN for evaluation by computation. The reaction rates calculated by infinite slab model with ANISN code agree well with the experiments when normalized at the source point where neutrons are incident on the grid plate shield. (auth.)

  4. A review of ANL base technology studies in support of the U.S. LMFBR vibration program

    International Nuclear Information System (INIS)

    Wambsganss, M.W.; Chen, S.S.; Mulcahy, T.M.; Shin, Y.S.

    1977-01-01

    Argonne National Laboratory (ANL) is the center for base technology studies of flow induced vibration for the U.S. LMFBR Program. This paper reviews and summarizes published results, reports on the status of ongoing programs, and discusses future needs as outlined in the U.S. LMFBR Vibrations Program Plan. (author)

  5. PHOEBUS/UHTREX: a preliminary study of a low-cost facility for transient tests of LMFBR fuel

    Energy Technology Data Exchange (ETDEWEB)

    Kirk, W.L. (comp.)

    1976-08-01

    The results of a brief preliminary design study of a facility for transient nuclear tests of fast breeder reactor fuel are described. The study is based on the use of a reactor building originally built for the UHTREX reactor, and the use of some reactor hardware and reactor design and fabrication technology remaining from the Phoebus-2 reactor of the Rover nulcear rocket propulsion program. The facility is therefore currently identified as the PHOEBUS/UHTREX facility. This facility is believed capable of providing early information regarding fast reactor core accident energetics issues which will be very valuable to the overall LMFBR safety program. Facility performance in conjunction with a reference 127-fuel pin experiment is described. Low cost and early availability of the facility were emphasized in the selection of design features and parameters.

  6. Self sloshing of thermal-stratification interface in LMFBR hot plenum

    International Nuclear Information System (INIS)

    Tanaka, Nobukazu

    2010-01-01

    One of the important problems in thermal hydraulic designs for pool-type LMFBR is to properly estimate thermal conditions of the coolant that is liquid sodium affecting thermal stresses on the vessel or internal structures during both steady and transient operations. The severity of these conditions of pool-type reactor in Japan which will be reinforced and equipped with special devices for anti-seismic demands is apt to be much greater than loop-type due to large volume of coolant. Water tests and thermal hydraulic analyses were performed to investigate such conditions in our institute. Purpose of this report is to overview such investigations which were conducted yet. That is to estimate the effects of the elevations of UIS (Upper Internal Structure) discharge and IHX (Intermediate Heat Exchanger) intakes on flow patterns, free surface disturbance and thermal stratification in hot plenum. From the results of the experiments, suitable elevations could be recommended by comparing some thermal hydraulic characteristics and self sloshing of thermal interface called as internal standing wave was observed in certain limited ranges of Richardson number. (author)

  7. Specialists' meeting on theoretical modelling of LMFBR fuel pin behaviour. Summary report

    International Nuclear Information System (INIS)

    1979-12-01

    The purpose of the meeting was to provide an opportunity for exchanging views of theoretical modelling of LMFBR fuel pin behaviour and to summarise the IWGFR member countries' knowledge in this field. The special emphasis was placed on normal operating conditions. The technical part of the meeting was divided into six sessions, as follows: An overview of fuel modelling studies; Key factors and basic phenomena relevant to fuel pin behaviour modelling; Application to steady state operation and normal transients; Experimental validation through pins in service and specific irradiation experiments; Advanced fuels; and Brief review of existing codes. During the meeting, papers were presented by the delegates on behalf of their countries or organization. The papers, which are included in this report, were either in the form of a general survey of the subject, or on specific technical subjects. In each subject area presentations appropriate to the subject were made from the submitted papers. The presentations were followed by discussions of the questions raised and summary is made

  8. Effects of governing parameters on steady-state inter-wrapper flow in an LMFBR

    International Nuclear Information System (INIS)

    Moriya, Shoichi

    2001-01-01

    Hydraulic experiments were performed using a 1/8th scale rectangular model, based on a Japanese demonstration fast breeder reactor design, in order to study fundamental characteristics of interwrapper flows occurring under steady state conditions in an LMFBR. The steady state interwrapper flow of which direction was downward in the center region and upward in the peripheral region of a core barrel was observed because of the radial static pressure gradient in the upper part of the core barrel, produced by a core blockage effect resulting from an above core structure with a perforated skirt. Thermal stratification phenomena were moreover observed in the interwrapper region, created by the hot steady state interwrapper flow from an upper plenum and the cold leakage flow through the separated plate of the core barrel. The thermal interface was generated in higher part of the core barrel when the core blockage effect was smaller and Richardson number and the leakage flow rate ratio were larger. Significant temperature fluctuations occurred in the peripheral region of the core barrel, when the difference between the interface elevations in the center and peripheral regions of the core barrel was enough large. (author)

  9. Cross calibration of IRS-P4 OCM satellite sensor

    Digital Repository Service at National Institute of Oceanography (India)

    Suresh, T.; Desa, E.; Mascarenhas, A.A.M.Q.; Matondkar, S.G.P.; Naik, P.; Nayak, S.R.

    obtained from the radiative transfer simulations of IRS-P4 OCM and SeaWiFS. The chlorophyll a values derived using the calibrated IRS-P4 OCM are found to be comparable with those derived from SeaWiFS and in close agreement with the measured values...

  10. P4 ATPases - lipid flippases and their role in disease

    NARCIS (Netherlands)

    Folmer, Dineke E.; Elferink, Ronald P. J. Oude; Paulusma, Coen C.

    2009-01-01

    P4 ATPases (type 4 P-type ATPases) are multispan transmembrane proteins that have been implicated in phospholipid translocation from the exoplasmic to the cytoplasmic leaflet of biological membranes. Studies in Saccharomyces cerevisiae have indicated that P4 ATPases are important in vesicle

  11. LMFBR fuel-design environment for endurance testing, primarily of oxide fuel elements with local faults

    International Nuclear Information System (INIS)

    Warinner, D.K.

    1980-01-01

    The US Department of Energy LMFBR Lines-of-Assurance are briefly stated and local faults are given perspective with an historical review and definition to help define the constraints of LMFBR fuel-element designs. Local-fault-propagation (fuel-element failure-propagation and blockage propagation) perceptions are reviewed. Fuel pin designs and major LMFBR parameters affecting pin performance are summarized. The interpretation of failed-fuel data is aided by a discussion of the effects of nonprototypicalities. The fuel-pin endurance expected in the US, USSR, France, UK, Japan, and West Germany is outlined. Finally, fuel-failure detection and location by delayed-neutron and gaseous-fission-product monitors are briefly discussed to better realize the operational limits

  12. Implications and control of fuel-cladding chemical interaction for LMFBR fuel pin design

    International Nuclear Information System (INIS)

    Roake, W.E.

    1977-01-01

    Fuel-cladding-chemical-interaction (FCCI) is typically incorporated into the design of an LMFBR fuel pin as a wastage allowance. Several interrelated factors are considered during the evolution of an LMFBR fuel pin design. Those which are indirectly affected by FCCI include: allowable pin power, fuel restructuring, fission gas migration and release from the fuel, fuel cracking, fuel swelling, in-reactor cladding creep, cladding swelling, and the cladding mechanical strain. Chemical activity of oxygen is the most readily controlled factor in FCCI. Two methods are being investigated: control of total oxygen inventory by limiting fuel O/M, and control of oxygen activity with buffer metals

  13. LMFBR safety criteria: cost-benefit considerations under the constraint of an a priori risk criterion

    International Nuclear Information System (INIS)

    Hartung, J.

    1979-01-01

    The role of cost-benefit considerations and a priori risk criteria as determinants of Core Disruptive Accident (CDA)-related safety criteria for large LMFBR's is explored with the aid of quantitative risk and probabilistic analysis methods. A methodology is described which allows a large number of design and siting alternatives to be traded off against each other with the goal of minimizing energy generation costs subject to the constraint of both an a priori risk criterion and a cost-benefit criterion. Application of this methodology to a specific LMFBR design project is described and the results are discussed. 5 refs

  14. Multicell slug flow heat transfer analysis of finite LMFBR bundles

    Energy Technology Data Exchange (ETDEWEB)

    Yeung, M.K.; Wolf, L.

    1978-12-01

    An analytical two-dimensional, multi-region, multi-cell technique has been developed for the thermal analysis of LMFBR rod bundles. Local temperature fields of various unit cells were obtained for 7, 19, and 37-rod bundles of different geometries and power distributions. The validity of the technique has been verified by its excellent agreement with the THTB calculational result. By comparing the calculated fully-developed circumferential clad temperature distribution with those of the experimental measurements, an axial correction factor has been derived to account for the entrance effect for practical considerations. Moreover, the knowledge of the local temperature field of the rod bundle leads to the determination of the effective mixing lengths L/sub ij/ for adjacent subchannels of various geometries. It was shown that the implementation of the accurately determined L/sub ij/ into COBRA-IIIC calculations has fairly significant effects on intersubchannel mixing. In addition, a scheme has been proposed to couple the 2-D distributed and lumped parameter calculation by COBRA-IIIC such that the entrance effect can be implanted into the distributed parameter analysis. The technique has demonstrated its applicability for a 7-rod bundle and the results of calculation were compared to those of three-dimensional analyses and experimental measurements.

  15. Fire protection device for LMFBR spent fuel shipping casks

    International Nuclear Information System (INIS)

    Moss, M.; Heckman, R.C.

    1977-08-01

    This report describes the analysis and experimental evaluation of a device to provide fire protection for a shipping cask used to transport liquid metal fast breeder reactor (LMFBR) fuel rods. Thermal analyses of various fire protection schemes were conducted by means of the finite difference code, CINDA. The choice of materials for the cask body was determined to be less important than the dimensions and number of cooling fins attached to the cask. Of several protection methods considered, radiation/convection shields between the cooling fins looked most attractive; these were tested on a quarter-scale cask model. The shields consisted of bimetallic bands which expanded when heated, blocking the fire, and retracted when cooled. This automatic reversibility would allow the fins to dissipate internally generated heat of a full-size cask once the fire was out. Tests showed that, even in an asymmetric fire exposure, the bands expanded to provide protection to the cask. The directly exposed surface of the cask model, protected this way, reached a temperature of only 180 0 C compared with 295 0 C in the unprotected state, when subjected to a butane flame for 0.5 h at a distance of 15 cm. Greater relative effectiveness could be expected in an engulfing fire in which the bands would expand more symmetrically

  16. LMFBR plant design features for sodium spill and fire protection

    International Nuclear Information System (INIS)

    Palm, R.E.

    1982-01-01

    Design features have been developed for an LMFBR plant to protect the concrete structures from potential liquid spills and fires and prevent sodium-concrete reactions. The inclusion of these features in the plant design reduces the severity of design basis accident conditions imposed on containment and other critical plant structures. Steel liners are provided in cells containing radioactive sodium systems, and catch pans are located in non-radioactive sodium system cells. The design requirements and descriptions of each of these protective features are presented. The loading conditions, analytical approach and numerical results are also included. Design of concrete cell structures that are subject to high temperature effects from sodium spills is discussed. The structural design considers the influence of high temperature on design properties of concrete and carbon steel materials based on results of a comprehensive test program. The development of these design features and high temperature design considerations for the Clinch River Breeder Reactor Plant (CRBRP) are presented in this paper

  17. Statistical mechanical analysis of LMFBR fuel cladding tubes

    International Nuclear Information System (INIS)

    Poncelet, J.-P.; Pay, A.

    1977-01-01

    The most important design requirement on fuel pin cladding for LMFBR's is its mechanical integrity. Disruptive factors include internal pressure from mixed oxide fuel fission gas release, thermal stresses and high temperature creep, neutron-induced differential void-swelling as a source of stress in the cladding and irradiation creep of stainless steel material, corrosion by fission products. Under irradiation these load-restraining mechanisms are accentuated by stainless steel embrittlement and strength alterations. To account for the numerous uncertainties involved in the analysis by theoretical models and computer codes statistical tools are unavoidably requested, i.e. Monte Carlo simulation methods. Thanks to these techniques, uncertainties in nominal characteristics, material properties and environmental conditions can be linked up in a correct way and used for a more accurate conceptual design. First, a thermal creep damage index is set up through a sufficiently sophisticated clad physical analysis including arbitrary time dependence of power and neutron flux as well as effects of sodium temperature, burnup and steel mechanical behavior. Although this strain limit approach implies a more general but time consuming model., on the counterpart the net output is improved and e.g. clad temperature, stress and strain maxima may be easily assessed. A full spectrum of variables are statistically treated to account for their probability distributions. Creep damage probability may be obtained and can contribute to a quantitative fuel probability estimation

  18. Control rod experiments in Racine

    International Nuclear Information System (INIS)

    Stanculescu, A.; Humbert, G.

    1981-09-01

    A survey of the control-rod experiments planned within the joint CEA/CNEN-DeBeNe critical experiment RACINE is given. The applicability to both heterogeneous and homogeneous large power LMFBR-cores is discussed. Finally, the most significant results of the provisional design calculations performed on behalf of the RACINE control-rod programme are presented

  19. Subassembly faults diagnostic of an LMFBR type reactor by the measurement of temperature noise

    International Nuclear Information System (INIS)

    Kokorev, B.V.; Palkin, I.I.; Turchin, N.M.; Pallagi, D.; Horanyi, S.

    1979-09-01

    The subassembly faults detection possibility by temperature noise analysis of an LMFBR is described. The paper contains the results of diagnostical examinations obtained on electrically heated NaK test rigs. On the basis of these results the measurement of temperature noise RMS value seems to be a practicable method to detect local blockages in an early phase. (author)

  20. A LMFBR for thorium utilization and for the U233/Th fuel rods specification

    International Nuclear Information System (INIS)

    Ishiguro, Y.; Dias, A.F.

    1982-01-01

    The use of U 233 /Th as fuel in the middle part of LMFBR core and the Pu/U in the external part of the core, are proposed. The basic neutronic and safety characteristics and the specifications of fuel rods to be used in the internal core, are presented. (E.G.) [pt

  1. LARA: Expert system for acoustic localization of robot in a LMFBR

    International Nuclear Information System (INIS)

    Lhuillier, C.; Malvache, P.

    1986-12-01

    The expert system LARA (Acoustic Localization of Autonomic Robot) has been developed to show the interest of introducing artificial intelligency for fine automatic positioning of refuelling machine in a LMFBR reactor. LARA which is equipped with an acoustic detector gives rapidly a good positioning on the fuel [fr

  2. Input parameters to codes which analyze LMFBR wire wrapped bundles. Revision 1

    International Nuclear Information System (INIS)

    Wang, S.F.; Todreas, N.E.

    1979-05-01

    This report provides a current summary of recommended values of key input parameters required for ENERGY code analysis of LMFBR wire wrapped bundles. This data is based on the interpretation of experimental results from the MIT and other available laboratory programs

  3. The state of art of the methods for thermohydraulics design of LMFBR fuel elements

    International Nuclear Information System (INIS)

    Fernandez y Fernandez, E.; Carajilescov, P.

    1981-09-01

    The present (experimental and analytical) state of art of the methods for thermohydraulics design of LMFBR fuel elements is analyzed. A development program is suggested, in order to obtain a computer code for modelling the distribution of coolant enthalpy in reactor core. This computer code is in development. (Author) [pt

  4. Crystallization of recombinant Haemophilus influenzaee (P4) acid phosphatase

    Energy Technology Data Exchange (ETDEWEB)

    Ou, Zhonghui [Department of Biochemistry, University of Missouri-Columbia, Columbia, MO 65211 (United States); Felts, Richard L. [Department of Chemistry, University of Missouri-Columbia, Columbia, MO 65211 (United States); Reilly, Thomas J. [Department of Veterinary Pathobiology and Veterinary Medical Diagnostic Laboratory, University of Missouri-Columbia, Columbia, MO 65211 (United States); Nix, Jay C. [Molecular Biology Consortium, Lawrence Berkeley National Laboratory, Berkeley, CA 94720 (United States); Tanner, John J., E-mail: tannerjj@missouri.edu [Department of Biochemistry, University of Missouri-Columbia, Columbia, MO 65211 (United States); Department of Chemistry, University of Missouri-Columbia, Columbia, MO 65211 (United States)

    2006-05-01

    Lipoprotein e (P4) is a class C acid phosphatase and a potential vaccine candidate for nontypeable H. influenzae infections. This paper reports the crystallization of recombinant e (P4) and the acquisition of a 1.7 Å resolution native X-ray diffraction data set. Haemophilus influenzae infects the upper respiratory tract of humans and can cause infections of the middle ear, sinuses and bronchi. The virulence of the pathogen is thought to involve a group of surface-localized macromolecular components that mediate interactions at the host–pathogen interface. One of these components is lipoprotein e (P4), which is a class C acid phosphatase and a potential vaccine candidate for nontypeable H. influenzae infections. This paper reports the crystallization of recombinant e (P4) and the acquisition of a 1.7 Å resolution native X-ray diffraction data set. The space group is P4{sub 2}2{sub 1}2, with unit-cell parameters a = 65.6, c = 101.4 Å, one protein molecule per asymmetric unit and 37% solvent content. This is the first report of the crystallization of a class C acid phosphatase.

  5. Synthesis Report on the understanding of failed LMFBR fuel element performance

    International Nuclear Information System (INIS)

    Plitz, H.; Bagley, K.; Harbourne, B.

    1990-07-01

    In the coarse of LMFBR operation fuel element failures cannot entirely be avoided as experienced during the operation of PFR, PHENIX and KNK II, where 44 failed fuel elements have been registered between 1978 and 1989. In earlier irradiations, post irradiation examinations showed mixed oxide pin diameter increases up to pin pitch distance, urging to stress reactor safety questions on the potential of fuel pin failure propagation within pin bundles. The chemical interaction of sodium with mixed oxide fuel is regarded to be the key for the understanding of failed fuel behavior. Valuable results on the failed fuel pin behavior during operation were obtained from the SILOE sodium loop test. Based on the bulk of experience with the detection of fuel pin failures, with the continued operation and with the handling of failed pins respectively elements, one can state: 1. All fuel pin failures have been detected securely in time and have been located. 2. Small defects are developing slowly. 3. Even large defects at end-of-life pins resulted in limited fuel loss. 4. Clad failures behave benign in main aspects. 5. The chemical interaction of sodium with mixed oxide is an important factor in the behavior of failed fuel pins, especially at high burnup. 6. Despite different pin designs and different operation conditions, on the basis of 44 failed elements in PFR, PHENIX and KNK II no pin-to-pin propagation was observed and fuel release was rather low, often not detectable. 7. In no case hazard conditions affecting reactor safety have been experienced

  6. The benefits and problems of base seismic isolation for LMFBR reactor plants

    International Nuclear Information System (INIS)

    Seidensticker, R.W.

    1988-01-01

    The use of seismic isolation as an approach to aseismic design has gained increasing interest as a viable and efficient engineering solution to earthquake ground motion both within and outside of the nuclear field. Seismic isolation design is fundamentally different from conventional design practice. In the conventional approach, seismic loads are resisted by making the structures, equipment, piping, and associated supports strong enough to resist seismic loads and to provide high levels of ductility. The use of seismic isolation approaches the problem by decoupling the structure (and its contents) from the seismic input resulting from ground shaking. Because LMFBR systems operate at virtually atmospheric pressure, vessels, piping, and associated components tend to be quite thin-walled. The problem is that these thin-walled items have little inherent resistance to earthquake effects and are vulnerable to seismic load effects. As a result, earthquake loads have an even greater influence on LMR designs than they already are in LWR plants. The potential benefits of seismic isolation for an LMR plant are considerable, including minimization of high-cost commodities such as stainless steel, large reductions in internal equipment loads, increased margins of safety for beyond-design-basis loads, and enhancement of plant standardization design. There are, of course, a number of issues and concerns in the use of seismic isolation for a nuclear power plant. These issues cover a number of items such as the lack of experience in actual earthquakes, effects of long-period ground motion, effect of vertical loads, traveling waves, and other related concerns. This paper presents an evaluation of the benefits and problems in the use of seismic isolation in LMR plants. 12 refs, 7 figs

  7. SIMMER-I: an S/sub n/, Implicit, Multifield, Multicomponent, Eulerian, Recriticality code for LMFBR disrupted core analysis

    International Nuclear Information System (INIS)

    Bell, C.R.; Bleiweis, P.B.; Boudreau, J.E.; Parker, F.R.; Smith, L.L.

    1976-08-01

    Physical models, numerical methods, and program description are presented for SIMMER-I, a computer program which predicts the neutronic and fluid dynamic behavior of an LMFBR during a hypothetical core disruptive accident

  8. Collaborative Occupational Therapy: Teachers' Impressions of the Partnering for Change (P4C) Model.

    Science.gov (United States)

    Wilson, A L; Harris, S R

    2018-05-01

    Occupational therapists (OTs) often face barriers when trying to collaborate with teachers in school-based settings. Partnering for change (P4C), a collaborative practice model designed to support children with developmental coordination disorder, could potentially support all students with special needs. Therefore, the aim of this study was to explore how teachers experience OT services delivered using the P4C model to support children with a variety of special needs. P4C was implemented at one elementary school in Courtenay, British Columbia. Eleven teachers participated in two focus groups and a one-on-one interview to gather descriptive, qualitative data. Grounded theory techniques were used for data analysis. Four themes (collaborating in the thick of it all, learning and taking risks, managing limited time and resources, and appreciating responsive OT support) represented teachers' experiences of P4C. Teachers strongly preferred collaborative OT services based on the P4C model. Students with a variety of special needs were supported within their classrooms as teachers learned new strategies from the OT and found ways to embed these strategies into their daily routines.

  9. Towards the structure of yeast and mammalian P4-ATPases

    DEFF Research Database (Denmark)

    Lyons, Joseph; Laban, Milena; Mikkelsen, Stine

    2017-01-01

    and biochemical studies of yeast and mammalian P4-ATPases, in particular the phosphatidylserine (PS) transporting Drs2p/Cdc50p (Saccharomyces cerevisiae) and bATP8A2/CDC50A (Bos taurus). However, questions surrounding the mechanism of lipid translocation remain. To address this deficit in knowledge and to provide...

  10. First LQCD Physics Runs with MILC and P4RHMC

    International Nuclear Information System (INIS)

    Soltz, R; Gupta, R

    2007-01-01

    An initial series of physics LQCD runs were submitted to the BG/L science bank with the milc and p4rhmc. Both runs were for lattice dimensions of 32 2 x 8. The p4 calculation was performed with v2.0 QMP( ) MPI.X (semioptomized p4 code using qmp over mpi) and milc v7.2, also using RHMC, but not specifically optimized for BlueGene. Calculations were performed along lines of constant physics, with the light quark masses 2-3 times their physics values and the strange quark mass set by m ud = 0.1m s . Job submissions was performed using the standard milc and p4 scripts provided on the ubgl cluster. Initial thermalized lattices for each code were also provided in this way. The only modifications for running on BG/L were to the directory names and the mT parameter which determines job durations (24 hrs on BG/L vs. 4 hrs on ubgl). The milc scripts were set to resubmit themselves 10 times, and the p4 scripts were submitted serially using the ''psub -d'' job dependency option. The runp4rhmc.tcsh could not be used to resubmit due to the 30m time limit imposed on interactive jobs. Most jobs were submitted to the smallest, 512 node partitions, but both codes could also run on the 1024 node partitions with a gain of only 30-50%. The majority of jobs ran without error. Stalled jobs were often indicative of a communication gap within a partition that LC was able to fix quickly. On some occasion a zero-length lattice file was deleted to allow jobs to restart successfully. Approximately 1000 trajectories were calculated for each beta value, see Table . The analysis was performed with the standard analysis scripts for each code, make( ) summary.pl for milc and analysis.tcsh for p4rhmc. All lattices, log files, and job submission scripts have been archived to permanent storage for subsequent analysis

  11. Single-phase sodium pump model for LMFBR thermal-hydraulic analysis

    International Nuclear Information System (INIS)

    Madni, I.K.; Cazzoli, E.G.; Agrawal, A.K.

    1979-01-01

    A single-phase, homologous pump model has been developed for simulation of safety-related transients in LMFBR systems. Pump characteristics are modeled by homologous head and torque relations encompassing all regimes of operation. These relations were derived from independent model test results with a centrifugal pump of specific speed equal to 35 (SI units) or 1800 (gpm units), and are used to analyze the steady-state and transient behavior of sodium pumps in a number of LMFBR plants. Characteristic coefficients for the polynomials in all operational regimes are provided in a tabular form. The speed and flow dependence of head is included through solutions of the impeller and coolant dynamic equations. Results show the model to yield excellent agreement with experimental data in sodium for the FFTF prototype pump, and with vendor calculations for the CRBR pump. A sample pipe rupture calculation is also performed to demonstrate the necessity for modeling the complete pump characteristics

  12. Evaluation of air cleaning system concepts for emergency use in LMFBR plants

    International Nuclear Information System (INIS)

    Hilliard, R.K.; McCormack, J.D.; Postma, A.K.

    1976-12-01

    Nineteen different air cleaning concepts are arranged into twenty-four systems and evaluated for use as accident mitigating systems in LMFBR plants. Both single, low-leakage containment plants and once-through operation applicable to containment/confinement plants are considered. Plant characteristics affecting air cleaning requirements are defined for 1000 MW(e) plants and a sodium and radiological release term is postulated. The accident conditions under which the emergency air cleaning system (EACS) must function is established by use of SOFIRE-II and HAA-3B computer codes. Criteria are developed for evaluating the various systems and for assigning comparative ratings. The numerical ratings are combined with information on cost and development potential to arrive at recommendations for the most promising systems. The conclusion is made that reliable and effective systems are feasible for use as engineered safety features for LMFBR plants, but that development effort is required for all the air cleaning concepts evaluated

  13. Contribution of Clinch River Breeder Reactor plant design and development to the LMFBR fuel cycle

    International Nuclear Information System (INIS)

    Riley, D.R.; Dickson, P.W.

    1981-01-01

    This paper describes how the CRBRP development and CRBRP focus of the LMFBR base technology program have led to advances in the state of the art in physics, thermal-hydraulics, structural analysis, core restraint, seismic analysis, and analysis of hypothetical core-disruptive accident energetics, all of which have been incorporated through disciplined engineering into the final CRBRP design. The total development in the US of fuels and materials, the analytical advances made on CRBRP design, and the incorporation of the latest experimental results into that design have put the US technology in general and the CRBRP design in particular at the forefront of technology. This has placed the US in a position to develop the most favorable LMFBR fuel cycle

  14. Post-test analysis of PANDA test P4

    International Nuclear Information System (INIS)

    Hart, J.; Woudstra, A.; Koning, H.

    1999-01-01

    The results of a post-test analysis of the integral system test P4, which has been executed in the PANDA facility at PSI in Switzerland within the framework of Work Package 2 of the TEPSS project are presented. The post-test analysis comprises an evaluation of the PANDA test P4 and a comparison of the test results with the results of simulations using the RELAPS/MOD3.2, TRAC-BF1, and MELCOR 1.8.4 codes. The PANDA test P4 has provided data about how trapped air released from the drywell later in the transient affects PCCS performance in an adequate manner. The well-defined measurements can serve as an important database for the assessment of thermal hydraulic system analysis codes, especially for conditions that could be met in passively operated advanced reactors, i.e. low pressure and small driving forces. Based on the analysis of the test data, the test acceptance criteria have been met. The test P4 has been successfully completed and the instrument readings were with the permitted ranges. The PCCs showed a favorable and robust performance and a wide margin for decay heat removal from the containment. The PANDA P4 test demonstrated that trapped air, released from the drywell later in the transient, only temporarily and only slightly affected the performance of the passive containment cooling system. The analysis of the results of the RELAPS code showed that the overall behaviour of the test has been calculated quite well with regards to pressure, mass flow rates, and pool boil-down. This accounts both for the pre-test and the post-test simulations. However, due to the one-dimensional, stacked-volume modeling of the PANDA DW, WW, and GDCS vessels, 3D-effects such as in-vessel mixing and recirculation could not be calculated. The post-test MELCOR simulation showed an overall behaviour that is comparable to RELAPS. However, MELCOR calculated almost no air trapping in the PCC tubes that could hinder the steam condensation rate. This resulted in lower calculated

  15. Acoustic detection for water/steam leak from a tube of LMFBR steam generator

    International Nuclear Information System (INIS)

    Sonoda, Masataka; Shindo, Yoshihisa

    1989-01-01

    Acoustic leak detector is useful for detecting more quickly intermediate leak than the existing hydrogen detector and is available for identification of leak location on the accident of water/steam leak from a tube of LMFBR steam generator. This paper presents the overview of HALD (High frequency Acoustics Leak Detection) system, which is more sensitive for leak detection and lower cost of equipment for identification of leak location than a low frequency type detector. (author)

  16. Instrumentation for core and coolant monitoring in liquid-metal fast breeder reactors (LMFBR)

    International Nuclear Information System (INIS)

    Hess, B.; Ruppert, E.

    1975-01-01

    The review on core and coolant instrumentation for liquid metal fast breeders aims to give a short survey of measurement methods and the variety of appropriate instrumentation developed and tested for reactor application throughout the world. The introductory part gives a general outline of instrumentation development, partly as the refinement of well-known thermal reactor instrumentation and partly as the special instrumentation demanded for LMFBR safety requirements, some aspects of which are also discussed briefly. The in-core LMFBR instrumentation is surveyed, classifying the measurement or monitoring of coolant properties such as temperature, pressure, flow and acoustic emission and the measurement of core-kinetic quantities such as neutron flux and reactivity. Without considering the fundamentals of the measurements, the state of instrument development is reviewed and, where known, future aspects are indicated. An additional review on fuel failure detection methods and the related instrumentation distinguishes between global or whole-core detection methods and those used for localization of failures. Special attention is paid to the aspect of reactor safety and its reliability as one of the major objectives of these detection methods. A summary of the protective systems and instrumentation already used or foreseen for LMFBR plants forms a transition to a very brief discussion of handling and interpretation of the multitude of data derived from the rather comprehensive LMFBR instrumentation. This state of the art review claims neither to be complete at the time published nor to be a detailed guide to special problems of instrumentation development, the solutions to which are normally part of industrial knowhow. (author)

  17. A survey of LMFBR cavitation technology in the U.S.A

    International Nuclear Information System (INIS)

    Cha, Y.S.; Huebotter, P.R.; Hopenfeld, J.

    1976-01-01

    Several experimental programmes of a basic and applied nature were established in the USA in order to develop guidelines to ensure design and operation of LMFBR hydraulic components free from cavitation and/or cavitation damage. As of March 1976, most of these experimental programs are still in progress. Each programme is briefly described. The available interium data are presented. References that are relevant are provided

  18. LMFBR conceptual design study: an overview of environmental and safety concerns

    International Nuclear Information System (INIS)

    Brenchley, D.L.

    1981-06-01

    The US Department of Energy (DOE) initiated the Liquid Metal Fast Breeder (LMFBR) Conceptual Design Study (CDS) with the objective of maintaining a viable breeder option. The project is scheduled to be completed in FY-1981 but decisions regarding plant construction will be delayed until at least 1985. This report provides a review of the potential environmental and safety engineering concerns for the CDS and recommends specific action for the Environmental and Safety Engineering Division of DOE

  19. Development of an 85,000 gpm (19,303 m3/h) LMFBR primary pump

    International Nuclear Information System (INIS)

    Zerinvary, M.C.; Wagner, E.W.

    1984-01-01

    The development of an 85,000 gpm two-stage primary pump for liquid metal fast breeder reactor (LMFBR) applications is described. The design was supported by air and cavitation model testing of the hyraulics, and development and feature testing of the level control system and the adjustable frequency solid state power supply. Important fabrication and water test items are also discussed, along with some unique assembly tooling requirements

  20. Fretting and wear of stainless and ferritic steels in LMFBR steam generators

    International Nuclear Information System (INIS)

    Lewis, M.W.J.; Campbell, C.S.

    1981-01-01

    Steam generators for LMFBR's may be subject to both fretting wear as a result of flow-induced vibrations and to wear from larger amplitude sliding movements from thermal changes. Results of tests simulating the latter are given for stainless and ferritic steels. For the assessment of fretting wear damage, vibration assessments must be combined with data on specific wear rates. Test mechanisms used to study fretting in sodium covering impact, impact-slide and pure rubbing are described and results presented. (author)

  1. LMFBR conceptual design study: an overview of environmental and safety concerns

    Energy Technology Data Exchange (ETDEWEB)

    Brenchley, D.L.

    1981-06-01

    The US Department of Energy (DOE) initiated the Liquid Metal Fast Breeder (LMFBR) Conceptual Design Study (CDS) with the objective of maintaining a viable breeder option. The project is scheduled to be completed in FY-1981 but decisions regarding plant construction will be delayed until at least 1985. This report provides a review of the potential environmental and safety engineering concerns for the CDS and recommends specific action for the Environmental and Safety Engineering Division of DOE.

  2. Seismic criteria studies and analyses. Quarterly progress report No. 3. [LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    1975-01-03

    Information is presented concerning the extent to which vibratory motions at the subsurface foundation level might differ from motions at the ground surface and the effects of the various subsurface materials on the overall Clinch River Breeder Reactor site response; seismic analyses of LMFBR type reactors to establish analytical procedures for predicting structure stresses and deformations; and aspects of the current technology regarding the representation of energy losses in nuclear power plants as equivalent viscous damping.

  3. A fundamental study on sodium-water reaction in the double-pool-type LMFBR

    International Nuclear Information System (INIS)

    Yoshida, Kazuo; Akimoto, Tokuzo

    1987-01-01

    In order to evaluate the pressure rise by large sodium-water reaction in the Double-Pool LMFBR, basic tests on pressure wave celerity in rectangular tube are carried out. The initial spike pressure in rectangular-shelled steam generator of the Double Pool reactor, strongly depends on pressure wave celerity. In this study, celerity was measured as a function of pressure wave rising time and pulse height, and influence of water around the test section on celerity was investigated. (author)

  4. Regulatory Mechanisms in the P4-ATPase Complex

    DEFF Research Database (Denmark)

    Costa, Sara

    . The functionality on the P4-ATPase complex is essential for several cellular processes, such as vesicle-mediated transport. However, the specific role of flippase activity in vesicle biogenesis and the regulatory mechanism behind this process is still poorly understood. In these studies, we identified...... as these transporters are trapped in an environment formed by their own substrate (lipids). Most lipid uptake assays use fluorescent lipid analogues in combination with flow cytometry analysis. However, flow cytometry systems are rather expensive and require extensive maintenance. Thus, we present a simple and more...

  5. Systems Biology and P4 Medicine: Past, Present, and Future

    Directory of Open Access Journals (Sweden)

    Leroy Hood

    2013-04-01

    Full Text Available Studying complex biological systems in a holistic rather than a “one gene or one protein” at a time approach requires the concerted effort of scientists from a wide variety of disciplines. The Institute for Systems Biology (ISB has seamlessly integrated these disparate fields to create a cross-disciplinary platform and culture in which “biology drives technology drives computation.” To achieve this platform/culture, it has been necessary for cross-disciplinary ISB scientists to learn one another’s languages and work together effectively in teams. The focus of this “systems” approach on disease has led to a discipline denoted systems medicine. The advent of technological breakthroughs in the fields of genomics, proteomics, and, indeed, the other “omics” is catalyzing striking advances in systems medicine that have and are transforming diagnostic and therapeutic strategies. Systems medicine has united genomics and genetics through family genomics to more readily identify disease genes. It has made blood a window into health and disease. It is leading to the stratification of diseases (division into discrete subtypes for proper impedance match against drugs and the stratification of patients into subgroups that respond to environmental challenges in a similar manner (e.g. response to drugs, response to toxins, etc.. The convergence of patient-activated social networks, big data and their analytics, and systems medicine has led to a P4 medicine that is predictive, preventive, personalized, and participatory. Medicine will focus on each individual. It will become proactive in nature. It will increasingly focus on wellness rather than disease. For example, in 10 years each patient will be surrounded by a virtual cloud of billions of data points, and we will have the tools to reduce this enormous data dimensionality into simple hypotheses about how to optimize wellness and avoid disease for each individual. P4 medicine will be able to

  6. 85,000-GPM, single-stage, single-suction LMFBR intermediate centrifugal pump

    International Nuclear Information System (INIS)

    Fair, C.E.; Cook, M.E.; Huber, K.A.; Rohde, R.

    1983-01-01

    The mechanical and hydraulic design features of the 85,000-gpm, single-stage, single-suction pump test article, which is designed to circulate liquid-sodium coolant in the intermediate heat-transport system of a Large-Scale Liquid Metal Fast Breeder Reactor (LS-LMFBR), are described. The design and analytical considerations used to satisfy the pump performance and operability requirements are presented. The validation of pump hydraulic performance using a hydraulic scale-model pump is discussed, as is the featute test for the mechanical-shaft seal system

  7. LMFBR steam generator development: duplex bayonet tube steam generator. Volume II

    International Nuclear Information System (INIS)

    DeFur, D.D.

    1975-04-01

    This report represents the culmination of work performed in fulfillment of ERDA Contract AT(11-1)-2426, Task Agreement 2, in which alternate steam generator designs were developed and studied. The basic bayonet tube generator design previously developed by C-E under AEC Contract AT(11-1)-3031 was expanded by incorporating duplex heat transfer tubes to enhance the unit's overall safety and reliability. The effort consisted of providing and evaluating conceptual designs of the evaporator, superheater and reheater components for a large plant LMFBR steam generator (950 MWt per heat transport loop)

  8. Bubble behavior in LMFBR core disruptive accidents. Annual report, June 1, 1975--June 30, 1976

    International Nuclear Information System (INIS)

    Reynolds, A.B.; Erdman, C.A.; Garner, P.L.; Kennedy, M.F.; Rao, S.P.; Refling, J.G.

    1976-08-01

    The work reported here is part of the Aerosol Release and Transport program for LMFBR safety assessment for the Reactor Safety Research Division of the U.S. Nuclear Regulatory Commission. Six areas were at various stages of investigation during this reporting period. A study of nonequilibrium mass transfer during fuel expansion and a study of the dynamics of fuel expansion into the sodium pool were completed. Studies are underway on condensation on above-core structures and on generation of aerosols from condensation. Studies were initiated on small-particle generation from hydrodynamic fragmentation, on particle kinematics and on particle-surface interaction

  9. Safety research needs for carbide and nitride fueled LMFBR's. Final report

    International Nuclear Information System (INIS)

    Kastenberg, W.E.

    1975-01-01

    The results of a study initiated at UCLA during the academic year 1974--1975 to evaluate and review the potential safety related research needs for carbide and nitride fueled LMFBR's are presented. The tasks included the following: (1) Review Core and primary system designs for any significant differences from oxide fueled reactors, (2) Review carbide (and nitride) fuel element irradiation behavior, (3) Review reactor behavior in postulated accidents, (4) Examine analytical methods of accident analysis to identify major gaps in models and data, and (5) Examine post accident heat removal. (TSS)

  10. Transference of advanced LMFBR control technology to the aerospace power system program

    International Nuclear Information System (INIS)

    Chisholm, G.H.

    1984-01-01

    Much recent R and D has been devoted to the safety of liquid metal fast breeder reactors (LMFBR's). Part of the resulting technology, especially advanced control systems, appears to be directly transferable to the space nuclear power program. Some of the ideas described herein have been already culminated in successful products that are available for application, e.g. analytical redundancy and fault-tolerant computers. Others, in various stages of R and D, are being developed as elements to support the design goals outlined in the following section, e.g. automated software verification, automated hardware verification, and system validation

  11. Analytical treatment of large leak pressure behavior in LMFBR steam generators

    International Nuclear Information System (INIS)

    Hori, Masao; Miyake, Osamu

    1980-07-01

    Simplified analytical methods applicable to the estimation of initial pressure spike in case of a large leak accident in LMFBR steam generators were devised as follows; (i) Estimation of the initial water leak rate by the centered rarefaction wave method, (ii) Estimation of the initial pressure spike by the one-dimensional compressible method with either the columnar bubble growth model or the spherical bubble growth model. These methods were compared with relevant experimental data or other more elaborate analyses and validated to be usable in simple geometry and limited time span cases. Application of these methods to an actual steam generator case was explained and demonstrated. (author)

  12. Analysis of hypothetical LMFBR whole-core accidents in the USA

    International Nuclear Information System (INIS)

    Ferguson, D.R.; Deitrich, L.W.; Brown, N.W.; Waltar, A.E.

    1978-01-01

    The issue of hypothetical whole-core accidents continues to play a significant role in assessment of the potential risk to the public associated with LMFBR operation in the USA. The paper briefly characterizes the changing nature of this role, with emphasis on the current risk-oriented perspective. It then describes the models and codes used for accident analysis in the USA which have been developed under DOE sponsorship and summarizes some specific applications of the codes to the current generation of fast reactors. An assessment of future trends in this area concludes the paper

  13. SUPERENERGY-2: a multiassembly, steady-state computer code for LMFBR core thermal-hydraulic analysis

    Energy Technology Data Exchange (ETDEWEB)

    Basehore, K.L.; Todreas, N.E.

    1980-08-01

    Core thermal-hydraulic design and performance analyses for Liquid Metal Fast Breeder Reactors (LMFBRs) require repeated detailed multiassembly calculations to determine radial temperature profiles and subchannel outlet temperatures for various core configurations and subassembly structural analyses. At steady-state, detailed core-wide temperature profiles are required for core restraint calculations and subassembly structural analysis. In addition, sodium outlet temperatures are routinely needed for each reactor operating cycle. The SUPERENERGY-2 thermal-hydraulic code was designed specifically to meet these designer needs. It is applicable only to steady-state, forced-convection flow in LMFBR core geometries.

  14. Comparative analysis of quality assurance requirements for selected LMFBR components of classes 1, 2 and 3

    International Nuclear Information System (INIS)

    Kleinert, K.P.

    1992-01-01

    The study analyses and compares German, French, British and Italian practices and procedures applied for various LMFBR projects both related to the quality assurance system and related to the particular type of class of component:Class 1: primary reactor vessel; Class 2: Secondary sodium pump; Class 3: Primary cold trap. Various areas of analysis and comparison were selected to identify the underlying concepts of grading of requirements and measures, to identify the similarities and differences, and to give recommendations for further actions concerning quality assurance requirements 60 refs., 21 tabs., 6 figs

  15. Study of structural attachments of a pool type LMFBR vessel through seismic analysis of a simplified three dimensional finite element model

    International Nuclear Information System (INIS)

    Ahmed, H.; Ma, D.

    1979-01-01

    A simplified three dimensional finite element model of a pool type LMFBR in conjunction with the computer program ANSYS is developed and scoping results of seismic analysis are produced. Through this study various structural attachments of a pool type LMFBR like the reactor vessel skirt support, the pump support and reactor shell-support structure interfaces are studied. This study also provides some useful results on equivalent viscous damping approach and some improvements to the treatment of equivalent viscous damping are recommended. This study also sets forth pertinent guidelines for detailed three dimensional finite element seismic analysis of pool type LMFBR

  16. Thiophilic metal ion rescue of phosphorothioate interference within the Tetrahymena ribozyme P4-P6 domain.

    OpenAIRE

    Basu, S; Strobel, S A

    1999-01-01

    Divalent metal ions are essential for the folding and catalytic activities of many RNAs. A commonly employed biochemical technique to identify metal-binding sites in RNA is the rescue of Rp alpha-phosphorothioate (PS) interference by the addition of soft divalent metal ions. To access the ability of such experiments to accurately identify metal-ion coordinations within a complex RNA fold, we report metal-rescue results from the Tetrahymena group I intron P4-P6 domain, where the location and c...

  17. In service monitoring and servicing after leak detection for the LMFBR steam generators of Phenix and Superphenix

    International Nuclear Information System (INIS)

    Castelnau; Desmas; Lapicore.

    1980-10-01

    Great care must be taken to minimize the probability of leaks within LMFBR steam generators. In this paper, the following topics are discussed: leak prevention; description of monitoring devices (hydrogen monitoring, acoustic monitoring) and protection devices; automatic and manual actions; leak localization (with or without sodium dumping); post-leak inspection and repair

  18. International Atomic Energy Agency specialist meeting on advances in structural analysis for LMFBR applications. Summary report

    International Nuclear Information System (INIS)

    Perez, M.A.; Roche, R.L.

    1983-05-01

    After the first session on review of national positions in the subject field, the meeting was divided into five technical sections as follows: General methods of Structural Analysis for Elevated Temperatures; Inelastic Analysis Methods for Elevated Temperature; Effects of Cyclic loading; Design Codes and Criteria; Instability and Buckling - Piping Analysis in the Creep Range. The conclusions of the Meeting were summarised as follows. In view of the complexity of material behaviour and the variability of properties from cast to cast, continuing work is needed to develop simple constitutive relations which ensure an acceptable level of conservatism for design evaluations. It is recognized that simplified design methods require further development for the assessment of ratchetting and shakedown of high temperature structures. More development work is required in the areas of buckling elastic follow up weld factors and these developments should take account of the imperfections inherent in welded fabrications. There is a need for realistic tests on welded structural features to validate design methods. It is proposed that this subject would be the topic of a future specialists meeting. In several countries, organisations are now preparing Guides and Codes concerning Structural Assessment for LMFBR components. It seems that some of these Codes could be drafted within a few years. In order to make a more realistic assessment of LMFBR structures, defect assessment in elevated temperature range must be considered

  19. Model-based temperature noise monitoring methods for LMFBR core anomaly detection

    International Nuclear Information System (INIS)

    Tamaoki, Tetsuo; Sonoda, Yukio; Sato, Masuo; Takahashi, Ryoichi.

    1994-01-01

    Temperature noise, measured by thermocouples mounted at each core fuel subassembly, is considered to be the most useful signal for detecting and locating local cooling anomalies in an LMFBR core. However, the core outlet temperature noise contains background noise due to fluctuations in the operating parameters including reactor power. It is therefore necessary to reduce this background noise for highly sensitive anomaly detection by subtracting predictable components from the measured signal. In the present study, both a physical model and an autoregressive model were applied to noise data measured in the experimental fast reactor JOYO. The results indicate that the autoregressive model has a higher precision than the physical model in background noise prediction. Based on these results, an 'autoregressive model modification method' is proposed, in which a temporary autoregressive model is generated by interpolation or extrapolation of reference models identified under a small number of different operating conditions. The generated autoregressive model has shown sufficient precision over a wide range of reactor power in applications to artificial noise data produced by an LMFBR noise simulator even when the coolant flow rate was changed to keep a constant power-to-flow ratio. (author)

  20. Detection of oscillatory components in noise signals and its application to fast detection of sodium boiling in LMFBR's

    International Nuclear Information System (INIS)

    Ehrhardt, J.

    1975-09-01

    In general, the surveillance of technical plants is performed by observating the mean value of measured signals. In this method not all information included in these signals is used. On the other hand - for example in a reactor - disturbances are possible which generate small oscillatory components in the measured signals. In general, these oscillatory components do not influence the mean value of the signals and consequently do not activate the conventional control system; however they can be found by analysis of the signal's noise component. For the detection of these oscillatory signals the observation of the frequency spectra of the noise signals is particularly advantageous because they produce peaks at the oscillation frequencies. In this paper a new detection system for the fast detection of suddenly appearing peaks in the frequency spectra of noise signals is presented. The prototype of a compact detection unit was developed which continuously computes the power spectral density (PSD) of noise signals and simultaneously supervises the PSD for peaks in the relevant frequency range. The detection method is not affected by the frequency dependance of the PSD and is applicable to any noise signal. General criteria were developed to enable the determination of the optimal detection system and its sensitivity. The upper limits of false alarm rate and detection time were taken into account. The detection criteria are applicable to all noise signals with approximately normally distributed amplitudes. Theoretical results were confirmed in a number of experiments; special experimental and theoretical parameter studies were done for the optimal detection of sodium boiling in LMFBR's. Computations based on these results showed that local and integral sodium boiling can be detected in a wide core range of SNR 300 by observing fluctuations of the neutron flux. In this connection it is important to point out that no additional core instrumentation is necessary because the

  1. French studies on local blockages in LMFBR fuel subassemblies

    International Nuclear Information System (INIS)

    Girard, C.; Jolas, P.; Seiler, J.M.

    1979-08-01

    This paper reviews experimental and theoretical studies done in FRANCE on the problem of partial subassembly blockages. The priorities are defined and the development of the French program in the European context is presented. Results of the out of pile experiments performed at CEA and EDF in single and two phases flow are given. A description of the main codes used to interpret these experiments is then shortly reviewed. It is found that the thermal behavior in single phase may be calculated with good precision, and that a simple semi-empirical formula can predict with good accuracy the number of channels blocked that lead to sodium boiling

  2. Intermolecular interaction of photoexcited Cu(/TMpy-P4) with water studied by transient resonance Raman and picosecond absorption spectroscopies

    NARCIS (Netherlands)

    Kruglik, S.; Kruglik, Sergei G.; Ermolenkov, Vladimir V.; Shvedko, Alexander G.; Orlovich, Valentine A.; Galievsky, Victor A.; Chirvony, Vladimir S.; Otto, Cornelis; Turpin, Pierre-Yves

    1997-01-01

    photoinduced complex between Cu(TMpy-P4) and water molecules, reversibly axially coordinated to the central metal, was observed in picosecond transient absorption and nanosecond resonance Raman experiments. This complex is rapidly created (τ1 = 15 ± 5 ps) in the excited triplet (π, π*) state of

  3. The safety of storage facilities for LMFBR spent fuels

    International Nuclear Information System (INIS)

    Lefort, G.; Puit, J.C.

    1982-04-01

    Storage conditions for the cooling of fast neutron spent fuel assembly, before reprocessing, will be adapted specifically to this fuel cycle, but in a preliminary testing period it is better to take advantage of the industrial storage conditions already used for spent fuel of light water reactors, even if no extrapolation is possible in the future. In this aim fuel assemblies are dismantled, as soon as thermal conditions allow it, and pins are gathered in leak proof containers in a gas atmosphere and put in a cooling pool. This solution gives good results but studies and experiments are resumed, for future processing, for safe, easy and economical transport and storage conditions [fr

  4. Laboratory-scale sodium-carbonate aggregate concrete interactions. [LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Westrich, H.R.; Stockman, H.W.; Suo-Anttila, A.

    1983-09-01

    A series of laboratory-scale experiments was made at 600/sup 0/C to identify the important heat-producing chemical reactions between sodium and carbonate aggregate concretes. Reactions between sodium and carbonate aggregate were found to be responsible for the bulk of heat production in sodium-concrete tests. Exothermic reactions were initiated at 580+-30/sup 0/C for limestone and dolostone aggregates as well as for hydrated limestone concrete, and at 540+-10/sup 0/C for dehydrated limestone concrete, but were ill-defined for dolostone concrete. Major reaction products included CaO, MgO, Na/sub 2/CO/sub 3/, Na/sub 2/O, NaOH, and elemental carbon. Sodium hydroxide, which forms when water is released from cement phases, causes slow erosion of the concrete with little heat production. The time-temperature profiles of these experiments have been modeled with a simplified version of the SLAM computer code, which has allowed derivation of chemical reaction rate coefficients.

  5. Pressure drop measurements in LMFBR wire wrapped blanket assemblies

    International Nuclear Information System (INIS)

    Chiu, C.; Hawley, J.; Rohsenow, W.M.; Todreas, N.E.

    1977-07-01

    In this experiment, measurements of subchannel static pressure for an interior and edge subchannel were taken at two elevations in two wire-wrapped 61-pin bundles. One of the bundles has geometric characteristics of P/D = 1.067 and H/D = 8.0 (4 inch lead length and 0.501 inch rod diameter) and the other bundle has geometric characteristics of P/D = 1.067 and H/D = 4.0 (2 inch lead length and 0.501 inch rod diameter). The bundle average friction factors as well as the local subchannel friction factors for both interior and edge subchannels were determined from the experimental static pressure data. The average subchannel flow rates for both edge and interior subchannels were determined in a separate experiment. Results show that two correlations suggested by Rehme and Novendstern for the bundle average friction factor cannot predict the data within the range of experimental error. The bundle average friction factors for both bundles under test were underestimated by Rehme's correlation and overestimated by Novendstern's correlation. The results of the local subchannel friction factors indicate the effect of the wire lead length is more pronounced in the interior subchannel friction factor than in the edge subchannel friction factor. As the wire wrap lead length decreases, both interior and edge subchannel friction factors increase

  6. Neutron noise induced by vibration on the French Phenix LMFBR

    International Nuclear Information System (INIS)

    Tigeot, Y.; Le Guillou, G.

    1977-01-01

    The vibratory measurements which are available on the reactor have simultaneously been recorded with the fluctuations of neutronic power measurements. The observations correspond to: a movement of the carrier concrete slab of the primary circuit at the fundamental frequency corresponding to the pumps rotary speed, a low level vibration on a control rod drive corresponding to an incipient defect, vibrations emergence on the core cover during a working cycle, and all the time, a resonance corresponding to the first vibrational mode of the fuel assemblies under the cooling sodium flow. The evidence of the vibratory movement has been obtained by the systematic calculation of the coherence function between the available neutronic noise measurements and the vibratory transducers. From the experience gained on PHENIX, vibration measurements are included in the SUPER PHENIX monitoring system

  7. Progress on acoustic techniques for LMFBR structural surveillance

    International Nuclear Information System (INIS)

    Burton, E.J.; Bentley, P.G.; McKnight, J.A.

    1980-01-01

    Acoustic techniques are being developed to monitor remotely the incipient events of various modes of failure. Topics have been selected from the development programme which are either of special importance or in which significant advances have been made recently. Ultrasonic inspection of stainless steel welds is difficult and one alternative approach which is being explored is to identify manufacturing defects during fabrication by monitoring the welding processes. Preliminary measurements are described of the acoustic events measured during deliberately defective welding tests in the laboratory and some initial analysis using pattern recognition techniques is described. The assessment of structural failures using probability analysis has emphasised the potential value of continuous monitoring during operation and this has led to the investigation into the use of vibrational analysis and acoustic emission as monitoring techniques. Mechanical failure from fatigue may be anticipated from measurement of vibrational modes and experience from PFR and from models have indicated the depth of detailed understanding required to achieve this. In the laboratory a vessel with an artificial defect has been pressurised to failure. Detection of the weak stress wave emissions was possible but difficult and the prospects for on-line monitoring are discussed. Ultrasonic technology for providing images of components immersed in the opaque sodium of LMFBRs is being developed. Images are cormed by the physical scanning of a target using transducers in a pulse-echo mode. Lead zirconate transducers have been developed which can be deployed during reactor shut-down. The first application will be to examine a limited area of the core of PFR. Handling the data from such an experiment involves developing methods for reading and storing the information from such ultrasonic echo. Such techniques have been tested in real time by simulation in a water model. Methods of enhancing the images to be

  8. Materials properties utilization in a cumulative mechanical damage function for LMFBR fuel pin failure analysis

    International Nuclear Information System (INIS)

    Jacobs, D.C.

    1977-01-01

    An overview is presented of one of the fuel-pin analysis techniques used in the CRBRP program, the cumulative mechanical damage function. This technique, as applied to LMFBR's, was developed along with the majority of models used to describe the mechanical properties and environmental behavior of the cladding (i.e., 20 percent cold-worked, 316 stainless steel). As it relates to fuel-pin analyses the Cumulative Mechanical Damage Function (CDF) continually monitors cladding integrity through steady state and transient operation; it is a time dependent function of temperature and stress which reflects the effects of both the prior mechanical history and the variations in mechanical properties caused by exposure to the reactor environment

  9. Single-phase pump model for analysis of LMFBR heat transport systems

    International Nuclear Information System (INIS)

    Madni, I.K.; Cazzoli, E.

    1978-05-01

    A single-phase pump model for transient and steady-state analysis of LMFBR heat transport systems is presented. Fundamental equations of the model are angular momentum balance to determine transient impeller speed and mass balance (including thermal expansion effects) to determine the level of sodium in the pump tank. Pump characteristics are modeled by homologous head and torque relations. All regions of pump operation are represented with reverse rotation allowed. The model also includes option for enthalpy rise calculations and pony motor operation. During steady state, the pump operating speed is determined by matching required head with total load in the circuit. Calculated transient results are presented for pump coastdown and double-ended pipe break accidents. The report examines the influence of frictional torque and specific speed on predicted response for the pump coastdown to natural circulation transient. The results for a double-ended pipe break accident indicate the necessity of including all regions of operation for pump characteristics

  10. Collection and evaluation of salt mixing data with the real time data acquisition system. [LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Glazer, S.; Chiu, C.; Todreas, N.E.

    1977-09-01

    A minicomputer based real time data acquisition system was designed and built to facilitate data collection during salt mixing tests in mock ups of LMFBR rod bundles. The system represents an expansion of data collection capabilities over previous equipment. It performs steady state and transient monitoring and recording of up to 512 individual electrical resistance probes. Extensive real time software was written to govern all phases of the data collection procedure, including probe definition, probe calibration, salt mixing test data acquisition and storage, and data editing. Offline software was also written to permit data examination and reduction to dimensionless salt concentration maps. Finally, the computer program SUPERENERGY was modified to permit rapid extraction of parameters from dimensionless salt concentration maps. The document describes the computer system, and includes circuit diagrams of all custom built components. It also includes descriptions and listings of all software written, as well as extensive user instructions.

  11. Wire-wrapped rod-bundle heat-transfer analysis for LMFBR

    International Nuclear Information System (INIS)

    Wong, C.N.C.; Todreas, N.E.

    1982-07-01

    Helical wire wraps are widely used in the LMFBR fuel and blanket assemblies to provide coolant mixing and maintain proper spacing between fuel pins. The presence of the helical wire, however, may possibly induce heat transfer problems, such as the uncertainty of the maximum clad temperature as a result of the contact between the wires and the pins. In this study, the detailed transient three dimensional velocity and temperature distributions for the coolant around the pin will be determined by solving the governing momentum and energy equation numerically. A computer code HEATRAN has been developed to perform this calculation. Before the computer code HEATRAN is applied to the wire wrapped rod bundle problem, it is used to analyze a wide range of fluid and heat transfer problem to verify its capabilities

  12. Stability of inner baffle-shell of pool type LMFBR - experimental and theoretical studies

    International Nuclear Information System (INIS)

    Lebey, J.; Combescure, A.

    1987-01-01

    I pool type LMFBR, the primary coolant circuit, inside the main vessel, comprises a hot plenum separated from a cold plenum by an inner baffle. For Superphenix 1 reactor, it was judged advisable to built a double-shell baffle, each shell withstanding only one type of loading (primary loading for one shell, secondary loading for the other). Due to the size and intricacy of the structure, this design involves unnegligible supplementary costs and manufacturing difficulties. Thus, an alternative solution has been studied for future plants projects. It consists of a single shell baffle having a shape especially studied to sustain the two types of applied loadings (thermal plus primary loadings). Such a shape was calculated by NOVATOME, and it was decided to check the ability of methods of analysis to predict the ruin of this structure under primary loading. For this purpose, a mock-up has been tested, and the experimental results compared with the calculated ones. (orig./GL)

  13. Analysis of pressure wave transients and seismic response in LMFBR piping systems using the SHAPS code

    International Nuclear Information System (INIS)

    Zeuch, W.R.; Wang, C.Y.

    1985-01-01

    This paper presents some of the current capabilities of the three-dimensional piping code SHAPS and demonstrates their usefulness in handling analyses encountered in typical LMFBR studies. Several examples demonstrate the utility of the SHAPS code for problems involving fluid-structure interactions and seismic-related events occurring in three-dimensional piping networks. Results of two studies of pressure wave propagation demonstrate the dynamic coupling of pipes and elbows producing global motion and rigorous treatment of physical quantities such as changes in density, pressure, and strain energy. Results of the seismic analysis demonstrate the capability of SHAPS to handle dynamic structural response within a piping network over an extended transient period of several seconds. Variation in dominant stress frequencies and global translational frequencies were easily handled with the code. 4 refs., 10 figs

  14. Active acoustic leak detection for LMFBR steam generator. Sound attenuation due to bubbles

    International Nuclear Information System (INIS)

    Kumagai, Hiromichi; Sakuma, Toshio

    1995-01-01

    In the steam generators (SG) of LMFBR, it is necessary to detect the leakage of water from tubes of heat exchangers as soon as it occurs. The active acoustic detection method has drawn general interest owing to its short response time and reduction of the influence of background noise. In this paper, the application of the active acoustic detection method for SG is proposed, and sound attenuation by bubbles is investigated experimentally. Furthermore, using the SG sector model, sound field characteristics and sound attenuation characteristics due to injection of bubbles are studied. It is clarified that the sound attenuation depends upon bubble size as well as void fraction, that the distance attenuation of sound in the SG model containing heat transfer tubes is 6dB for each two-fold increase of distance, and that emitted sound attenuates immediately upon injection of bubbles. (author)

  15. Status of the LMFBR thermo- and fluid-dynamic activities at KFK

    International Nuclear Information System (INIS)

    Hoffmann, H.; Hofmann, F.; Rehme, K.

    1979-01-01

    The aim of the thermo- and fluiddynamic analysis is to determine the spatial velocity and temperature distributions in LMFBR-core elements with high accuracy. Knowledge of these data is a necessary prerequisite for determining the mechanical behavior of fuel rods and of structural material. Three cases are distinguished: Nominal geometry and steady state conditions; non-nominal geometry and quasi-steady state conditions; nominal geometry and non-steady state conditions. The present situation for the design calculations of fuel elements is based mainly on undisturbed normal operation. Most of the thermo- and fluiddynamic activities performed under the Fast Breeder Programme at KFK are related to this case. The present status of theoretical and experimental research work briefly presented in this paper, can be subdivided into the following main topics: 1. Physical and mathematical modelling of single phase rod bundle thermo- and fluiddynamics, 2. Experimental investigations on heat transfer and fluid flow in rod bundles

  16. Material properties requirements for LMFBR structural design: general considerations and data needs

    International Nuclear Information System (INIS)

    Pugh, C.E.; Purdy, C.M.

    1977-01-01

    A statement is given of material properties information needed in connection with the structural design technology for liquid-metal fast breeder reactor (LMFBR) primary circuit components. Implementation of current analysis methods and criteria is considered with an emphasis on data and data correlations for performing elastic-plastic and creep analyses, for establishing allowable stress limits, and for computing creep-fatigue damage. Further development of the technology is discussed in relation to properties information. Emphasis is placed on improved constitutive equations for representing inelastic material behavior, on procedures for treating time-dependent fatigue, and on criteria for creep rupture. The properties are generally discussed without regard to specific alloys, since most categories of information are needed for each major structural material. Some sample experimental results are given for type 304 stainless steel and 2 1 / 4 Cr-1 Mo steel

  17. Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Todreas, N.E.; Cheng, S.K.; Basehore, K.

    1984-08-01

    This project principally undertook the investigation of the thermal hydraulic performance of wire wrapped fuel bundles of LMFBR configuration. Results obtained included phenomenological models for friction factors, flow split and mixing characteristics; correlations for predicting these characteristics suitable for insertion in design codes; numerical codes for analyzing bundle behavior both of the lumped subchannel and distributed parameter categories and experimental techniques for pressure velocity, flow split, salt conductivity and temperature measurement in water cooled mockups of bundles and subchannels. Flow regimes investigated included laminar, transition and turbulent flow under forced convection and mixed convection conditions. Forced convections conditions were emphasized. Continuing efforts are underway at MIT to complete the investigation of the mixed convection regime initiated here. A number of investigations on outlet plenum behavior were also made. The reports of these investigations are identified.

  18. Experimental plans for LMFBR cavity liner sodium spill test LT-1

    International Nuclear Information System (INIS)

    Hilliard, R.K.; Newell, G.A.

    1976-01-01

    Reinforced concrete is an important material of construction in LMFBR cavities and cells. Steel liners are often installed on the concrete surfaces to provide a gastight seal for minimizing air inleakage to inerted cell atmospheres and to protect the concrete from direct contact with sodium in the event of a sodium spill. In making safety assessment analyses, it is of interest to determine the adequacy of the liners to maintain their leaktightness during postulated accidents involving large sodium spills. However, data for basing analytical assessments of cell liners are very meager and an experimental program is underway at HEDL to provide some of the needed information. The HEDL cell liner evaluation program consists of both bench-scale feature tests and large-scale sodium spill demonstration tests. The plans for the first large-scale sodium spill test (LT-1) are the subject of this paper

  19. Sodium-NaK engineering handbook. Volume III. Sodium systems, safety, handling, and instrumentation. [LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Foust, O J [ed.

    1978-01-01

    The handbook is intended for use by present and future designers in the Liquid Metals Fast Breeder Reactor (LMFBR) Program and by the engineering and scientific community performing other type investigation and exprimentation requiring high-temperature sodium and NaK technology. The arrangement of subject matter progresses from a technological discussion of sodium and sodium--potassium alloy (NaK) to discussions of varius categories and uses of hardware in sodium and NaK systems. Emphasis is placed on sodium and NaK as heat-transport media. Sufficient detail is included for basic understanding of sodium and NaK technology and of technical aspects of sodium and NaK components and instrument systems. Information presented is considered adequate for use in feasibility studies and conceptual design, sizing components and systems, developing preliminary component and system descriptions, identifying technological limitations and problem areas, and defining basic constraints and parameters.

  20. TRANSENERGY S: computer codes for coolant temperature prediction in LMFBR cores during transient events

    International Nuclear Information System (INIS)

    Glazer, S.; Todreas, N.; Rohsenow, W.; Sonin, A.

    1981-02-01

    This document is intended as a user/programmer manual for the TRANSENERGY-S computer code. The code represents an extension of the steady state ENERGY model, originally developed by E. Khan, to predict coolant and fuel pin temperatures in a single LMFBR core assembly during transient events. Effects which may be modelled in the analysis include temporal variation in gamma heating in the coolant and duct wall, rod power production, coolant inlet temperature, coolant flow rate, and thermal boundary conditions around the single assembly. Numerical formulations of energy equations in the fuel and coolant are presented, and the solution schemes and stability criteria are discussed. A detailed description of the input deck preparation is presented, as well as code logic flowcharts, and a complete program listing. TRANSENERGY-S code predictions are compared with those of two different versions of COBRA, and partial results of a 61 pin bundle test case are presented

  1. Preliminary design: duplex tube low-pressure saturated steam generator for large LMFBR plant. Final report

    International Nuclear Information System (INIS)

    Dawson, B.E.

    1979-10-01

    A preliminary design was completed for a steam generator which is applicable to a four loop LMFBR plant of 1000 MWe gross output employing dry and saturated steam conditions. Two steam generators of 364 MWt thermal capacity would be in each loop. The steam generator is a straight, duplex tube design with a shell bellows for thermal expansion and a single tubesheet with an integral leak detection system. The report outlines a proposed series of development tasks to provide additional design data for the duplex tube and to demonstrate the steam generator design with test modules. The design can be adapted readily as either the evaporator or the superheater for a superheated steam cycle with temperatures up to at least 430 0 C (800 0 F), which is below the creep range for the 2 1/4 Cr-1 Mo material

  2. Influence of fission product transport on delayed neutron precursors and decay heat sources in LMFBR accidents

    International Nuclear Information System (INIS)

    Apperson, C.E. Jr.

    1981-01-01

    A method is presented for studying the influence of fission product transpot on delayed neutron precursors and decay heat sources during Liquid Metal Fast Breeder Reactor (LMFBR) unprotected accidents. The model represents the LMFBR core as a closed homogeneous cell. Thermodynamic phase equilibrium theory is used to predict fission product mobility. Reactor kinetics behavior is analyzed by an extension of point kinetics theory. Group dependent delayed neutron precursor and decay heat source retention factors, which represent the fraction of each group retained in the fuel, are developed to link the kinetics and thermodynamics analysis. Application of the method to a highly simplified model of an unprotected loss-of-flow accident shows a time delay on the order of 10 ms is introduced in the predisassembly power history if fission product motion is considered when compared to the traditional transient solution. The post-transient influence of fission product transport calculated by the present model is a 24 percent reduction in the decay heat level in the fuel material which is similar to traditional approximations. Isotopes of the noble gases, Kr and Xe, and the elements I and Br are shown to be very mobile and are responsible for a major part of the observed effects. Isotopes of the elements Cs, Se, Rb, and Te were found to be moderately mobile and contribute to a lesser extent to the observed phenomena. These results obtained from the application of the described model confirm the initial hypothesis that sufficient fission product transport can occur to influence a transient. For these reasons, it is concluded that extension of this model into a multi-cell transient analysis code is warranted

  3. Specialists' meeting on LMFBR fuel rod behaviour under operational transients, Kalpakkam, India, 3-6 December 1985

    International Nuclear Information System (INIS)

    1985-12-01

    IWGFR Specialists' Meeting on ''LMFBR Fuel Rod Behaviour Under Operational Transients'' was held in Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam during 3-6 December 1985. The meeting was attended by the representatives of Belgium, France, FRG, India, Italy, US, USSR, IAEA and observers from India. The purpose of the meeting was to provide a forum for the exchange of information on the subject of LMFBR Fuel Rod Behaviour Under Operational Transients. The meeting presentations were divided into sessions devoted to the following topics: Overview of National Programmes (3 papers); In-pile and out-pile experimental facilities and results (5 papers); Modelling and Code work (5 papers). A separate abstract was prepared for each of these papers

  4. LMFBR in-core thermal-hydraulics: the state of the art and US research and development needs

    International Nuclear Information System (INIS)

    Khan, E.U.

    1980-04-01

    A detailed critical review is presented of the literature relevant to predicting coolant flow and temperature fields in LMFBR core assemblies for nominal and non-nominal rod bundle geometries and reactor operating conditions. The review covers existing thermal-hydraulic models, computational methods, and experimental data useful for the design of an LMFBR core. The literature search made for this review included publications listed by Nuclear Science Abstracts and Energy Data Base as well as papers presented at key nuclear conferences. Based on this extensive review, the report discusses the accuracy with which the models predict flow and temperature fields in rod assemblies, identifying areas where analytical, experimental, and model development needs exist

  5. Development of models for the sodium version of the two-phase three-dimensional thermal hydraulics code THERMIT. [LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, G.J.; Kazimi, M.S.

    1980-05-01

    Several different models and correlations were developed and incorporated in the sodium version of THERMIT, a thermal-hydraulics code written at MIT for the purpose of analyzing transients under LMFBR conditions. This includes: a mechanism for the inclusion of radial heat conduction in the sodium coolant as well as radial heat loss to the structure surrounding the test section. The fuel rod conduction scheme was modified to allow for more flexibility in modelling the gas plenum regions and fuel restructuring. The formulas for mass and momentum exchange between the liquid and vapor phases were improved. The single phase and two phase friction factors were replaced by correlations more appropriate to LMFBR assembly geometry.

  6. Nonlinear transient deformation of LMFBR fuel elements under impulsive loading

    International Nuclear Information System (INIS)

    Liebe, R.

    1975-01-01

    Subject of this paper is the elastoplastic transient behavior of one subassembly under given space- and time-dependent pressure loading. The interaction of several colliding fuel elements including coolant dynamics is briefly discussed. Theoretical models: description is given of physical mechanisms (bending of the slender subassembly duct, flattening of the thin-walled hexagonal cross section, pin-bundle and coolant action). Discrete structural models are compared and applied to the coupled fluid-structure problem. The use of a special beam element with lumped masses and discrete elastoplastic hinges with concentrated moments allows the effective simulation of the structure. An incompressible Eulerian nonstationary flow model including friction is used with a 4th order variable step Runge-Kutta method. Static and impact experiments: description is given of a single subassembly experimental program on a special droptower facility which is used for static and impact loading of 1:1 SNR-300 type fuel element models. Also described is a load and impact controlling device utilizing honeycomb crushing material which allows to produce desired pressure pulses (rise time, peak load, impulse, pulse shape). Forces, accelerations and strains are measured at the subassembly; its deformation is filmed with a high-speed camera and recorded by specially designed photodiode-arrays. Results and conclusions: good agreement is observed between experimental and theoretical response data. Parameter studies confirmed the significant role of duct flexure, local cross section flattening, material ductility and strain-hardening. The stiffening effects of the combined deformation of pin-bundle and spacer-grids is very strong, and most of the energy is dissipated by localized yielding of the hexcan

  7. Hydrodynamic behavior of a bare rod bundle. [LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Bartzis, J.G.; Todreas, N.E.

    1977-06-01

    The temperature distribution within the rod bundle of a nuclear reactor is of major importance in nuclear reactor design. However temperature information presupposes knowledge of the hydrodynamic behavior of the coolant which is the most difficult part of the problem due to complexity of the turbulence phenomena. In the present work a 2-equation turbulence model--a strong candidate for analyzing actual three dimensional turbulent flows--has been used to predict fully developed flow of infinite bare rod bundle of various aspect ratios (P/D). The model has been modified to take into account anisotropic effects of eddy viscosity. Secondary flow calculations have been also performed although the model seems to be too rough to predict the secondary flow correctly. Heat transfer calculations have been performed to confirm the importance of anisotropic viscosity in temperature predictions. All numerical calculations for flow and heat have been performed by two computer codes based on the TEACH code. Experimental measurements of the distribution of axial velocity, turbulent axial velocity, turbulent kinetic energy and radial Reynolds stresses were performed in the developing and fully developed regions. A 2-channel Laser Doppler Anemometer working on the Reference mode with forward scattering was used to perform the measurements in a simulated interior subchannel of a triangular rod array with P/D = 1.124. Comparisons between the analytical results and the results of this experiment as well as other experimental data in rod bundle array available in literature are presented. The predictions are in good agreement with the results for the high Reynolds numbers.

  8. Trip report: United States LMFBR Steam Generator Team. IAEA symposium, Bensberg, Germany, October 14--17, 1974

    International Nuclear Information System (INIS)

    1974-01-01

    Information is presented concerning steam generator design characteristics for the AFR reactor, SNR reactor, PHENIX reactor, SUPER PHENIX reactor, MONJU reactor, and BN-350 reactor; steam generator development programs for West Germany, France, Japan, U. K., and the U. S. S. R.; and the fabrication and inspection of steam generator components. Steam generator performance and maintenance requirements for operating LMFBR reactors are reviewed. (U.S.)

  9. Elaboration of a simplified method for LMFBR neutron calculations. Application to some problems related to research programs

    International Nuclear Information System (INIS)

    Zaetta, A.

    1982-11-01

    The topics includes two parts. 1) A calculation code specifically adapted to the parametric studies of LMFBR's cores in the neutronic field is presented. 2) A parametric study is made enabling comparison of the respective abilities to flatten flux and power distribution for the folloving core design: - homogeneous with variable compositions, - homogeneous with variable enrichments, - heterogeneous. The study shows the advantage of a hybrid concept on variable compositions and enrichments [fr

  10. Detailed design consideration on wire-spaced LMFBR fuel subassemblies under the effects of uncertainties and non-nominal geometries

    International Nuclear Information System (INIS)

    Hishida, H.

    1979-01-01

    This paper explains some analytical methods for evaluating the effects of deviation in subchannel coolant flow rate from the nominal value due to fuel pin bundle deflection and manufacturing tolerances and of inter-sub-channel coolant mixing and local temperature rise due to a wire-spacer on the hot spot temperature. Numerical results are given in each chapter with respect to a prototype LMFBR core. (author)

  11. Corrosion critique of the 2 1/4 Cr--1 Mo steel for LMFBR steam generation system applications

    International Nuclear Information System (INIS)

    Zima, G.E.

    1977-07-01

    The unstabilized ferritic steel of nominal composition, 2 1 / 4 Cr-1Mo, has been proposed for critical structural assignments in LMFBR powerplants, specifically: the tubing, tubesheet and shell of the evaporator and superheater components. The interest in this steel has been based on a presumably favorable general corrosion property spectrum, acceptable mechanical properties and fabricability, and certain economies associated with the low alloy content. This report is an attempt at a general corrosion assessment for the 2 1 / 4 Cr-1Mo steel and an identification of corrosion problem areas potential to this steel from the sodium and water/steam systems of the proposed working environment. There is a considerable area of uncertainty in the sodium-side response of 2 1 / 4 Cr-1Mo steel, centered in the loss and redisposition of carbon during long-term exposure to sodium of various impurity backgrounds. It is submitted that present evidence relating to the water/steam-side corrosion behavior of the 2 1 / 4 Cr-1Mo steel, under nominal and conceivable perturbed environmental conditions, constitutes the principal concern for the proposed LMFBR powerplant applications of this steel. It is suggested that this unfavorable corrosion aspect represents an inherent limitation of the low alloy content of this steel, probably largely independent of melting and processing recourses, and it is a sufficient basis to question the incentive for a continuation of the collateral studies of this steel for the proposed LMFBR steam generation system assignments

  12. LMFBR core design codes based on experimental fast reactor 'JOYO' experiences

    International Nuclear Information System (INIS)

    Kumaoka, Yoshio; Aoki, Katsutada; Kawashima, Masatoshi.

    1982-01-01

    In order to design the core for a 1,000-MWe-class fast breeder reactor, many kinds of computer codes as design tools are needed for analyzing the multicore components, mechanical behavior, nuclear performance and the thermal hydraulic performance of the core, and for designing the fuel. To meet these needs, Toshiba has endeavored for many years to develop highly reliable computer codes for core design, some of which are described in this article, and to continue their improvement by verifying them with actual fast reactor operation data. Above all, a series of nuclear design codes named COSMOS was successfully applied to the core design of the Japanese experimental fast breeder reactor ''JOYO'', and the excellent agreement between designed values and actual measured data has concluded that Toshiba's nuclear design codes are very useful for application to future large core design. (author)

  13. Gamma heated subassembly for sodium boiling experiments

    Energy Technology Data Exchange (ETDEWEB)

    Artus, S.C.

    1975-01-01

    The design of a system to boil sodium in an LMFBR is examined. This design should be regarded as a first step in a series of boiling experiments. The reactor chosen for the design of the boiling apparatus is the Experimental Breeder Reactor-II (EBR-II), located at the National Reactor Testing Station in Idaho. Criteria broadly classified as design objectives and design requirements are discussed.

  14. Metalate-Mediated Functionalization of P4 by Trapping Anionic [Cp*Fe(CO)2(η1-P4)]− with Lewis Acids

    NARCIS (Netherlands)

    Borger, Jaap E.; Jongkind, Maarten K.; Ehlers, Andreas W.; Lutz, Martin; Slootweg, J. Chris; Lammertsma, Koop

    2017-01-01

    The development of selective functionalization strategies ofwhite phosphorus (P4) is important to avoid the current chlori-nated intermediates. The use of transition metals (TMs) couldlead to catalytic procedures, but these are severely hamperedby the high reactivity and unpredictable nature of the

  15. Hambatan dalam implementasi program perencanaan persalinan dan pencegahan komplikasi (P4K di Kabupaten Badung

    Directory of Open Access Journals (Sweden)

    Putri Mariani

    2014-02-01

    Full Text Available The family-centered safe birthing initiative (P4K is aimed to reduce maternal and newborn mortality rates. The P4K program involves the distribution of promotional stickers by community health care workers. In 2011, the coverage of the P4K had reached 100% of villages, and 98.9% of expectant mothers had attached the promotional sticker on a visible section of their homes. However, the process is reported not implemented using standard procedures before placing the sticker on their homes. This study is aimed to explore the barriers to the implementation of P4K in Badung. This study was descriptive qualitative using phenomenology approach. Data were collected using focus group discussion (FGD with 20 midwives and 10 cadres, in-depth interviews (with 6 expectant mothers and 3 husbands/family members and participant observation of P4K implementation in community health centers. Secondary data was obtained through relevant P4K document analysis. Informants were purposively selected using the criteria of 1 midwives already trained in P4K, 2 cadres already trained in P4K and 3 P4K participating expectant mothers. Research findings indicate that knowledge, attitude and mother’s and husband’s behaviour impact negatively upon program implementation. There is also an evident of lack of logistical support including: P4K administrational forms, IEC pamphlets and transportation costs. Midwives and participating healthcare providers were having a very good knowledge; however, their behaviour does not demonstrate this. The poor governance of centres and high mobility of expectant mothers are also impacted upon program implementation. Future recommendations include program widening of scope and upscale, increased logistical support, continual monitoring and evaluation, research into program funding governance as well as upscale involvement of stakeholders.

  16. Fluid structure interaction in LMFBR cores modelling by an homogenization method

    International Nuclear Information System (INIS)

    Brochard, D.

    1988-01-01

    The upper plenum of the internals of PWR, the steam generator bundle, the nuclear reactor core, may be schematically represented by a beam bundle immersed in a fluid. The dynamical study of such a system needs to take into account fluid structure interaction. A refined model at the scale of the tubes can be used but leads to a very difficult problem to solve even on the largest computers. The homogenization method allows to have an approximation of the fluid structure interaction for the global behaviour of the bundle. It consists of replacing the heterogeneous physical medium (tubes and fluid) by an equivalent homogeneous medium whose characteristics are determined from the resolution of a set of problems on the elementary cell. The aim of this paper is to present the main steps of the determination of this equivalent medium in the case of small displacements (acoustic behaviour of the fluid). Then an application to LMFBR core geometry has been realised, which shows the lowering effect on eigenfrequencies due to the fluid. Some comparisons with test results will be presented. 6 refs, 7 figs, 2 tabs

  17. KOELSCH, a computer code simulating mechanical HCDA consequences in LMFBR primary containment

    International Nuclear Information System (INIS)

    Lange, L.; Gerling, W.; Schlein, I.

    1981-01-01

    The computer code KOELSCH (Kontinuumsmechanik in Euler-Lagrange Darstellung und Schalentheorie) calculates problems of continuum mechanics in Euler-Lagrangian representation and with the use of shell theory. It is being developed for the advanced simulation of the mechanical loading and the response of the primary containment of a LMFBR in the case of an HCDA. The essential features of the code and examples of calculations are presented. For the hydrodynamics the theoretical basis is the 3D Euler-Lagrangian formulation of the hydrodynamic equations in general curved coordinates. This starting point assure optimum adaptation of the physical problem to the geometry to be considered. The options available in KOELSCH are - H1: quasi- 1D Euler-Lagrangian - H2: 2D Euler - H3: 3D Euler (only rigid boundaries possible). The structural dynamics is treated by 2D Lagrangian formalism in cylindrical coordinates. Two options are foreseen: - thin shells: membrane or shell theory - massive structures: full tensor properties of materials are included. Flexibility with respect to complex geometries is gained by surface integration of the governing equations over finite elements with 3 - 8 corners. (orig./GL)

  18. Boreside rotating ultrasonic tester for wastage determination of LMFBR-type steam generator tubes

    International Nuclear Information System (INIS)

    Neely, H.H.; Renger, H.L.

    1979-01-01

    Large sodium-water reaction (SWR) leak tests are being run in near-prototypic steam generators at prototypic plant conditions of the Liquid Metal Fast Breeder Reactor (LMFBR). These tests simulate various types of steam tube failure at predetermined locations. A SWR results in a highly energetic-exothermic-caustic reaction which erodes neighboring tubes. A boreside-rotating ultrasonic inspection device was developed to measure wall thickness and inside diameter of the 2/one quarter/Cr-1 Mo, 10.1 mm I.D. steam tubes. Rotation of the UT beam yields a complimentary scan of the full tube in a single pass. The UT system was designed with a 15 MHz transducer in pulse-echo compression-wave mode at a pulse rate of 10,000/second. The UT beam is rotated at 20 r/s on a 1.27 mm pitch. System outputs are diameter, wall thickness, attitude, and axial position. Measurements are processed, then fed to a CRT and computer for later retrieval and plotting

  19. Calculation of Doses Due to Accidentally Released Plutonium From An LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Fish, B.R.

    2001-08-07

    Experimental data and analytical models that should be considered in assessing the transport properties of plutonium aerosols following a hypothetical reactor accident have been examined. Behaviors of released airborne materials within the reactor containment systems, as well as in the atmosphere near the reactor site boundaries, have been semiquantitatively predicted from experimental data and analytical models. The fundamental chemistry of plutonium as it may be applied in biological systems has been used to prepare models related to the intake and metabolism of plutonium dioxide, the fuel material of interest. Attempts have been made to calculate the possible doses from plutonium aerosols for a typical analyzed release in order to evaluate the magnitude of the internal exposure hazards that might exist in the vicinity of the reactor after a hypothetical LMFBR (Liquid-Metal Fast Breeder Reactor) accident. Intake of plutonium (using data for {sup 239}Pu as an example) and its distribution in the body were treated parametrically without regard to the details of transport pathways in the environment. To the extent possible, dose-response data and models have been reviewed, and an assessment of their adequacy has been made so that recommended or preferred practices could be developed.

  20. Thermohydraulic and thermal stress aspects of a porous blockage in an LMFBR fuel assembly

    International Nuclear Information System (INIS)

    Kuzay, T.M.; Marr, W.W.; Helenberg, H.W.; Ariman, T.; Wilson, R.E.; Pedersen, D.R.

    1979-01-01

    The current safety scenarios of Liquid Metal Fast Breeder Reactors (LMFBR) under local fault propagation include the study of a hypothetical accident initiated by the formation of an external debris porous blockage in a fuel subassembly. In this preliminary experimental and analytical investigation, a non-heat-generating porous blockage was postulated to cover 18 flow channels of a 37 pin Fast Test Reactor (FTR) type fuel subassembly. The axial extent of the blockage is 50 mm. The blockage material is stainless steel (SS 316) with 30 percent average porosity (percent void volume). The blockage and the pins were modeled with a finite element technique and the thermal field in the blockage was predicted. This thermal field was utilized to do a planar thermal stress analysis of the postulated blockage. To verify the analytical model and also to better understand the thermal-hydraulics of such a porous blockage out-of-pile tests were conducted in a sodium loop. Data from the out-of-pile tests was utilized to calibrate and improve the analytical model

  1. Measurement of heat and momentum eddy diffusivities in recirculating LMFBR outlet plenum flows

    International Nuclear Information System (INIS)

    Manno, V.P.; Golay, M.W.

    1978-06-01

    An optical technique has been developed for the measurement of the eddy diffusivity of heat in a transparent flowing medium. The method uses a combination of two established measurement tools: a Mach-Zehnder interferometer for the monitoring of turbulently fluctuating temperature and a Laser Doppler Anemometer (LDA) for the measurement of turbulent velocity fluctuations. The technique is applied to the investigation of flow fields characteristic of the LMFBR outlet plenum. The study is accomplished using air as the working fluid in a small scale Plexiglas test section. Lows are introduced into both the 1 / 15 scale FFTF outlet plenum and the 3 / 80 scale CRBR geometry plenum at inlet Reynolds numbers of 22,000. Measurements of the eddy diffusivity of heat and the eddy diffusivity of momentum are performed at a total of 11 measurement stations. Significant differences of the turbulence parameters are found between the two geometries, and the higher chimney structure of the CRBR case is found to be the major cause of the distinction. Spectral intensity studies of the fluctuating electronic analog signals of velocity and temperature are also performed. Error analysis of the overall technique indicates an experimental error of 10% in the determination of the eddy diffusivity of heat and 6% in the evaluation of turbulent momentum viscosity. In general it is seen that the turbulence in the cases observed is not isotropic, and use of isotropic turbulent heat and momentum diffusivities in transport modelling would not be a valid procedure

  2. Noise and DC balanced outlet temperature signals for monitoring coolant flow in LMFBR fuel elements

    International Nuclear Information System (INIS)

    Edelmann, M.

    1977-01-01

    Local cooling disturbances in LMFBR fuel elements may have serious safety implications for the whole reactor core. They have to be detected reliably in an early stage of their formation therefore. This can be accomplished in principle by individual monitoring of the coolant flow rate or the coolant outlet temperature of the sub-assemblies with high precision. In this paper a method is proposed to increase the sensitivity of outlet temperature signals to cooling disturbances. Using balanced temperature signals provides a means for eliminating the normal variations from the original signals which limit the sensitivity and speed of response to cooling disturbances. It is shown that a balanced signal can be derived easily from the original temperature signal by subtracting an inlet temperature and a neutron detector signal with appropriate time shift. The method was tested with tape-recorded noise signals of the KNK I reactor at Karlsruhe. The experimental results confirm the theoretical predictions. A significant reduction of the uncertainty of measured outlet temperatures was achieved. This enables very sensitive and fast response monitoring of coolant flow. Furthermore, it was found that minimizing the variance of the balanced signal offers the possibility for a rough determination of the heat transfer coefficient of the fuel rods during normal reactor operation at power. (author)

  3. Effect of heat input patterns on temperature distribution in LMFBR blanket assemblies

    International Nuclear Information System (INIS)

    Engel, F.C.; Markley, R.A.; Minushkin, B.

    1980-01-01

    Heat transfer tests were conducted over a wide range of sodium flow rates and heat input using a full scale, vertical, electrical-resistance heated rod bundle simulating conditions in a breeder reactor blanket assembly. The rod bundle was extensively instrumented with thermocouples located at six different elevations in the wire wrap spacers and inside the cladding to map temperature distributions in the rod bundle. The rod heat input had a 1.4:1 maximum-to-average axial cosine shape. Rod heat input powers simulating a number of power distributions in LMFBR Radial and Inner Blanket Assemblies were established. The resulting transverse temperature profiles across the rod bundle are presented for three elevations for tests of about 440 kW heat input and gpm flow. The temperature distribution was found to follow the heat input profile but is modified by mixing and the flow distribution over side and inside flow subchannels. These profiles were compared with predictions of a subchannel computer code of the marching type

  4. Small sodium-to-gas leak behavior in relation to LMFBR leak detection system design

    International Nuclear Information System (INIS)

    Hopenfeld, J.; Taylor, G.R.; James, L.A.

    1976-01-01

    Various aspects of sodium-to-gas leaks which must be considered in the design of leak detection systems for LMFBR's are discussed. Attention is focused primarily on small, weeping type leaks. Corrosion rates of steels in fused sodium hydroxide and corrosion damage observed at the site of small leaks lead to the conclusion that the sodium-gas reaction products could attack the primary hot leg piping at rates up to 0.08 mils per hour. Based on theoretical considerations of the corrosion mechanism and on visual observations of pipe topography following small sodium leak tests, it is concluded that pipe damage will be manifested by the formation of small detectable leaks prior to the appearance of larger leaks. The case for uniform pipe corrosion along the pipe circumference or along a vertical section of the pipe is also examined. Using a theoretical model for the gravity flow of sodium and reaction products along the pipe surface and a mass transport controlled corrosion process, it is shown that below sodium leak rates of about 30 g/hr for the primary piping corrosion damage will not extend beyond one radius distance from the leak site. A method of estimating the time delay between the initiation of such leaks and the development of a larger leak due to increased pipe stresses resulting from corrosion is presented

  5. LMFBR Emergency Deployment Assuming 45 year Time-Delay Excess CO{sub 2} Removal

    Energy Technology Data Exchange (ETDEWEB)

    Schenewerk, William Ernest [5060 San Rafael Avenue, Los Angeles, CA, 90042-3239 (United States)

    2008-07-01

    Atmospheric CO{sub 2} is presently increasing 2.25% per year in proportion to 2.25% per year exponential fossil fuel consumption increase. CO{sub 2} removal is modeled as being proportional to 45-year-earlier CO{sub 2} amount above 280 ppmV-C. This is: Exp (-0.0225/year * 45 years) = 0.36 fraction CO{sub 2} removed from anthropological emissions, apparently by seawater. LMFBRs use 15 year doubling time. Deploying 30000 GWe atomic power by year-2080 results in CO{sub 2} doubling year-2065 if World primary energy consumption continues increasing 2.25% per year. CO{sub 2} remains roughly twice pre-industrial until year-2100. Beginning year-2080, CO{sub 2} declines at 2.25% per year. CO{sub 2} will presumably decline back to roughly the year-2000 value by year-2200 if the 45-year-delay sink remains effective. LMFBR and GCFR fleet expands to 30000 GWe by 2080. 1000 GWe LWR fleet consumes 5 Mt HM (Heavy Metal). Breeder first cores require 1 Mt HM. (author)

  6. Development of computer code models for analysis of subassembly voiding in the LMFBR

    International Nuclear Information System (INIS)

    Hinkle, W.

    1979-12-01

    The research program discussed in this report was started in FY1979 under the combined sponsorship of the US Department of Energy (DOE), General Electric (GE) and Hanford Engineering Development Laboratory (HEDL). The objective of the program is to develop multi-dimensional computer codes which can be used for the analysis of subassembly voiding incoherence under postulated accident conditions in the LMFBR. Two codes are being developed in parallel. The first will use a two fluid (6 equation) model which is more difficult to develop but has the potential for providing a code with the utmost in flexibility and physical consistency for use in the long term. The other will use a mixture (< 6 equation) model which is less general but may be more amenable to interpretation and use of experimental data and therefore, easier to develop for use in the near term. To assure that the models developed are not design dependent, geometries and transient conditions typical of both foreign and US designs are being considered

  7. Measurement of heat and momentum eddy diffusivities in recirculating LMFBR outlet plenum flows

    Energy Technology Data Exchange (ETDEWEB)

    Manno, V.P.; Golay, M.W.

    1978-06-01

    An optical technique has been developed for the measurement of the eddy diffusivity of heat in a transparent flowing medium. The method uses a combination of two established measurement tools: a Mach-Zehnder interferometer for the monitoring of turbulently fluctuating temperature and a Laser Doppler Anemometer (LDA) for the measurement of turbulent velocity fluctuations. The technique is applied to the investigation of flow fields characteristic of the LMFBR outlet plenum. The study is accomplished using air as the working fluid in a small scale Plexiglas test section. Lows are introduced into both the /sup 1///sub 15/ scale FFTF outlet plenum and the /sup 3///sub 80/ scale CRBR geometry plenum at inlet Reynolds numbers of 22,000. Measurements of the eddy diffusivity of heat and the eddy diffusivity of momentum are performed at a total of 11 measurement stations. Significant differences of the turbulence parameters are found between the two geometries, and the higher chimney structure of the CRBR case is found to be the major cause of the distinction. Spectral intensity studies of the fluctuating electronic analog signals of velocity and temperature are also performed. Error analysis of the overall technique indicates an experimental error of 10% in the determination of the eddy diffusivity of heat and 6% in the evaluation of turbulent momentum viscosity. In general it is seen that the turbulence in the cases observed is not isotropic, and use of isotropic turbulent heat and momentum diffusivities in transport modelling would not be a valid procedure.

  8. Evaluation of the structural integrity of LMFBR equipment cell liners: results of preliminary investigations

    International Nuclear Information System (INIS)

    McAfee, W.J.; Sartory, W.K.

    1976-01-01

    The behavior of a plane wall segment of a prototype liquid-metal-cooled fast breeder reactor (LMFBR) cell under conditions of a postulated massive sodium spill was studied. Sodium-concrete reaction calculations were performed assuming an initial flaw existed in the liner such that high-temperature sodium could penetrate to the concrete underneath. Based on existing sodium-concrete reaction rate data, bounding values were established for the maximum energy release per unit volume of concrete. The potential effect of this energy release on the deformation of the liner material was determined. The temperature buildup in the liner and the pressure differential across the flaw in the liner were also studied. The transient thermal and structural responses of the steel liner and backup concrete were analyzed in detail using the inelastic computer code ANSYS. The literature on the mechanical, physical, and general behavior properties of concrete at high temperature was reviewed. This review emphasized the structural behavior of concrete and did not cover the sodium-concrete reaction

  9. Post-accident fuel relocation and heat removal in the LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Kazimi, M S; Tsai, S S; Gasser, R D

    1976-08-01

    Assessment of the dynamics of post-accident fuel relocation and heat removal is an important aspect of the evaluation of the consequences of a hypothetical accident in an LMFBR. Such an assessment is of particular importance in the evaluation of the post-accident radiological doses around the reactor site. In the present evaluation particular attention is given to the design features of the Clinch River Breeder Reactor Plant (CRBR). Fuel relocation and heat removal, assuming certain conditions have resulted in core disruption, are discussed. The discussion of events and phenomena involved in the relocation processes is centered around the resulting patterns of heat source distribution. The factors influencing fuel relocation and distribution in the inlet and outlet plena of the reactor vessel are discussed. The current technology of in-vessel heat removal is applied to the design of the CRBR reactor. Both fuel debris cooling limits and overall coolant flow in the reactor under natural convection conditions are explored. Some of the uncertainties in ex-vessel fuel behavior are addressed. In particular, the effect of melting the cavity bed on the rate of growth of a molten fuel pool is investigated.

  10. Qualification testing program plan for SIMMER. A computer code for LMFBR disrupted core analysis

    International Nuclear Information System (INIS)

    Basdekas, D.L.; Silberberg, M.; Curtis, R.T.; Kelber, C.N.

    1978-07-01

    The objective of SIMMER qualification testing program is to assure that the mathematical models and input parameters are derived from experimental data, which, on the basis of criteria still to be established, are representative of the phenomena and processes governing the progression of a CDA in an LMFBR. At the present time, the work to meet this objective can be classified into three general task areas as they relate to the use of SIMMER in CDA analysis: (1) The whole-core energetic disassembly accident, or the ''vessel problem'': The objective here is to predict the partition of the total energy release, by a postulated severe power excursion, between the primary containment and the energy absorbed through nondestructive dissipative processes. (2) Single subassembly accident: The objective here is to determine the pertinent phenomena and to develop the capability to assess the significance and likelihood that such accidents might propagate to involvement of larger fraction of the core. (3) The whole-core transition phase accident: The objective here is to advance the understanding of the phenomena and processes involved, so that reliable predictions can be made of the possible consequences of a CDA and the potential for further nuclear excursions through recriticality

  11. Analysis and application of prestressed concrete reactor vessels for LMFBR containment

    International Nuclear Information System (INIS)

    Marchertas, A.H.; Fistedis, S.H.; Bazant, Z.P.; Belytschko, T.B.

    1978-01-01

    An analytical model of a prestressed concrete reactor vessel (PCRV) for LMFBR and the associated finite element computer code, involving an explicit time integration procedure, is described. The model is axisymmetric and includes simulations of the tensile cracking of concrete, the reinforcement, and a prestressing capability. The tensile cracking of concrete and the steel reinforcement are both modeled as continuously distributed within the finite element. The stresses in the reinforcement and concrete are computed separately and combined to give an overall stress state of the composite material. Attention is given to the fact that cracks do not form instantaneously, but develop gradually. Thus, after crack initiation the normal stress is reduced to zero gradually as a function of time. Residual shear resistance of cracks due to aggregate interlock is also taken into account. Prestressing of the PCRV is modeled by special structural members which represent an averaged prestressing layer equivalent to an axisymmetric shell. The internal prestressing members are superimposed over the reinforced concrete body of the PCRV; they are permitted to stretch and slide in a predetermined path, simulating the actual tendons. The validity of the code is examined by comparison with experimental data. (Auth.)

  12. An appreciation of the events, models and data used for LMFBR radiological source term estimations

    International Nuclear Information System (INIS)

    Keir, D.; Clough, P.N.

    1989-01-01

    In this report, the events, models and data currently available for analysis of accident source terms in liquid metal cooled fast neutron reactors are reviewed. The types of hypothetical accidents considered are the low probability, more extreme types of severe accident, involving significant degradation of the core and which may lead to the release of radionuclides. The base case reactor design considered is a commercial scale sodium pool reactor of the CDFR type. The feasibility of an integrated calculational approach to radionuclide transport and speciation (such as is used for LWR accident analysis) is explored. It is concluded that there is no fundamental obstacle, in terms of scientific data or understanding of the phenomena involved, to such an approach. However this must be regarded as a long-term goal because of the large amount of effort still required to advance development to a stage comparable with LWR studies. Particular aspects of LMFBR severe accident phenomenology which require attention are the behaviour of radionuclides during core disruptive accident bubble formation and evolution, and during the less rapid sequences of core melt under sodium. The basic requirement for improved thermal hydraulic modelling of core, coolant and structural materials, in these and other scenarios, is highlighted as fundamental to the accuracy and realism of source term estimations. The coupling of such modelling to that of radionuclide behaviour is seen as the key to future development in this area

  13. Haemophilus influenzae P4 Interacts With Extracellular Matrix Proteins Promoting Adhesion and Serum Resistance.

    Science.gov (United States)

    Su, Yu-Ching; Mukherjee, Oindrilla; Singh, Birendra; Hallgren, Oskar; Westergren-Thorsson, Gunilla; Hood, Derek; Riesbeck, Kristian

    2016-01-15

    Interaction with the extracellular matrix (ECM) is one of the successful colonization strategies employed by nontypeable Haemophilus influenzae (NTHi). Here we identified Haemophilus lipoprotein e (P4) as a receptor for ECM proteins. Purified recombinant P4 displayed a high binding affinity for laminin (Kd = 9.26 nM) and fibronectin (Kd = 10.19 nM), but slightly less to vitronectin (Kd = 16.51 nM). A P4-deficient NTHi mutant showed a significantly decreased binding to these ECM components. Vitronectin acquisition conferred serum resistance to both P4-expressing NTHi and Escherichia coli transformants. P4-mediated bacterial adherence to pharynx, type II alveolar, and bronchial epithelial cells was mainly attributed to fibronectin. Importantly, a significantly reduced bacterial infection was observed in the middle ear of the Junbo mouse model when NTHi was devoid of P4. In conclusion, our data provide new insight into the role of P4 as an important factor for Haemophilus colonization and subsequent respiratory tract infection. © The Author 2015. Published by Oxford University Press on behalf of the Infectious Diseases Society of America. All rights reserved. For Permissions, please e-mail: journals.permissions@oup.com.

  14. Physics & Preservice Teachers Partnership Project (P4): An interdisciplinary peer learning tool

    Science.gov (United States)

    Simmonds, Paul J.; Wenner, Julianne A.

    Physics graduate students (PGs) and teacher candidates (TCs) often graduate with specific weaknesses. PGs frequently lack training in teaching and effective communication. TCs are typically underprepared for teaching science, and physics in particular. In response to these challenges, we created P4 . P4 is an innovative model for peer learning, creating interdisciplinary partnerships that help college physics instructors train their students in the ``soft skills'' prized in both academia and industry, while helping teacher educators infuse more content knowledge into science methods courses. In P4, PGs plan a lesson and deliver physics content to TCs. TCs then use this content to design and execute a 15-minute elementary science lesson. Framed by the concept of peer learning, we expected P4 would help PGs develop their teaching and communication skills, and TCs learn more physics. We studied the affordances and constraints of P4 to inform future iterations. Overall, P4 was successful, with both PGs and TCs reporting benefits. Affordances for PGs included the chance to plan and teach a class; TCs benefitted from working with experts to increase content knowledge. We will share the full findings and implications of our study, and outline next steps for P4.

  15. The MVMp P4 promoter is a host cell-type range determinant in vivo.

    Science.gov (United States)

    Meir, Chen; Mincberg, Michal; Rostovsky, Irina; Tal, Saar; Vollmers, Ellen M; Levi, Adi; Tattersall, Peter; Davis, Claytus

    2017-06-01

    The protoparvovirus early promoters, e.g. P4 of Minute Virus of Mice (MVM), play a critical role during infection. Initial P4 activity depends on the host transcription machinery only. Since this is cell-type dependent, it is hypothesized that P4 is a host cell-type range determinant. Yet host range determinants have mapped mostly to capsid, never P4. Here we test the hypothesis using the mouse embryo as a model system. Disruption of the CRE element of P4 drastically decreased infection levels without altering range. However, when we swapped promoter elements of MVM P4 with those from equivalent regions of the closely related H1 virus, we observed elimination of infection in fibroblasts and chondrocytes and the acquisition of infection in skeletal muscle. We conclude that P4 is a host range determinant and a target for modifying the productive infection potential of the virus - an important consideration in adapting these viruses for oncotherapy. Copyright © 2017 Elsevier Inc. All rights reserved.

  16. Hambatan dalam Implementasi Program Perencanaan Persalinan dan Pencegahan Komplikasi (P4K) di Kabupaten Badung

    OpenAIRE

    Mariani, Putri

    2013-01-01

    The family-centered safe birthing initiative (P4K) is aimed to reduce maternal and newborn mortality rates. The P4K program involves the distribution of promotional stickers by community health care workers. In 2011, the coverage of the P4K had reached 100% of villages, and 98.9% of expectant mothers had attached the promotional sticker on a visible section of their homes. However, the process is reported not implemented using standard procedures before placing the sticker on their homes. Thi...

  17. USO DE ANTIOXIDANTES PARA MELHORAR A EFICIÊNCIA REPRODUTIVA DE REBANHO BOVINO SUBMETIDO A PROTOCOLO DE SINCRONIZAÇÃO COM PROGESTERONA (P4

    Directory of Open Access Journals (Sweden)

    Ricardo Zanella

    2010-10-01

    Full Text Available Estrus synchronization with progesterone is commonly used in farms with better reproductive control. Free radicals production, i.e. oxidative stress, is associated with progesterone levels. The oxidative stress is responsible for aggression to the cellular membrane, leading to a lise and lipoperoxide formation. In this work, the antioxidant compensatory effect (Vitamins C and E associated with the exogenous progesterone implant (P4, used in estrus synchronization protocols in cattle, was evaluated. Twenty-five cows were randomly selected in 5 different groups: 1 control without P4, 2 control with P4, 3 P4 + vitamin C and E, 4 P4 + vitamin E, 5 P4 + vitamin C. The lipid lipoperoxidation was measured trough Thiobarbituric acid reactive substances (TBA-RS and Glutatione Peroxidase enzyme (GSHpx at days 0 and 7 of the estrus synchronization protocol. The use of vitamin E, in this experiment, showed a better pregnancy rate, however, the results must be validated before orienting the use of the vitamin in cows synchronized with P4.

  18. Optimization of radially heterogeneous 1000-MW(e) LMFBR core configurations. Appendixes D and E. Research project 620-25

    International Nuclear Information System (INIS)

    Barthold, W.P.; Orechwa, Y.; Su, S.F.; Hutter, E.; Batch, R.V.; Beitel, J.C.; Turski, R.B.; Lam, P.S.K.

    1979-11-01

    A parameter study was conducted to determine the interrelated effects of: loosely or tightly coupled fuel regions separated by internal blanket assemblies, number of fuel regions, core height, number and arrangement of internal blanket subassemblies, number and size of fuel pins in a subassembly, etc. the effects of these parameters on sodium void reactivity, Doppler, incoherence, breeding gain, and thermohydraulics were of prime interest. Trends were established and ground work laid for optimization of a large, radially-heterogeneous, LMFBR core that will have low energetics in an HCDA and will have good thermal and breeding performance

  19. Safety criteria for the future LMFBR's in France and main safety issues for the rapide 1500 project

    International Nuclear Information System (INIS)

    Justin, F.; Natta, M.; Orzoni, G.

    1985-04-01

    The main safety criteria for future LMFBR in France and the related issues for the RAPIDE 1500 project are presented and discussed. The evolutions with respect to SUPERPHENIX options and requirements are emphasized, in particular for the concerns of the prevention of core melt accidents, fuel damage limits and related required performances of the protection system, since one main option is not to consider whole core melt accidents in the containment design. One shall also point out the advantages of some mitigating features which were nevertheless added in the containment design, although without any explicit consideration for core melt accidents

  20. Theory and use of GIRAFFE for analysis of decay characteristics of delayed-neutron precursors in an LMFBR

    International Nuclear Information System (INIS)

    Gross, K.C.

    1980-07-01

    The application of the computer code GIRAFFE (General Isotope Release Analysis For Failed Elements) written in FORTRAN IV is described. GIRAFFE was designed to provide parameter estimates of the nonlinear discrete-measurement models that govern the transport and decay of delayed-neutron precursors in a liquid-metal fast breeder reactor (LMFBR). The code has been organized into a set of small, relatively independent and well-defined modules to facilitate modification and maintenance. The program logic, the numerical techniques, and the methods of solution used by the code are presented, and the functions of the MAIN program and of each subroutine are discussed

  1. Review: P4-ATPases as Phospholipid Flippases-Structure, Function, and Enigmas

    DEFF Research Database (Denmark)

    Andersen, Jens P; Vestergaard, Anna L; Mikkelsen, Stine A

    2016-01-01

    -type ATPase signature sequence, and dephosphorylation is activated by the lipid substrate being flipped from the exoplasmic to the cytoplasmic leaflet similar to the activation of dephosphorylation of Na+/K+-ATPase by exoplasmic K+. How the phospholipid is translocated can be understood in terms...... group is propelled along against its concentration gradient with the hydrocarbon chains projecting out into the lipid phase by movement of an isoleucine located at the position corresponding to an ion binding glutamate in the Ca2+- and Na+/K+-ATPases. Hence, the P4-ATPase mechanism is quite similar...... on properties of mammalian and yeast P4-ATPases for which most mechanistic insight is available. However, the structure, function and enigmas associated with mammalian and yeast P4-ATPases most likely extend to P4-ATPases of plants and other organisms....

  2. Merging P4P and disease management: how do you know which one is working?

    Science.gov (United States)

    Smith, Allen L

    2007-03-01

    An intervention movement in managed care, disease management (DM), is a system of coordinated health care interventions and communication for populations with conditions in which patient self-care efforts are significant. Another managed care intervention movement, pay for performance (P4P), involves an incentive component in which payment is defined based on meeting specific, previously agreed-upon process or outcomes targets. To explore the various characteristics of DM and P4P interventions, determine how they differ, and explore the differences in results of programs in current practice. In DM, regular ongoing evaluation of clinical, humanistic, and economic outcomes plays a crucial role in reducing costs and improving quality of care. The goal of improving overall patient health in DM is also accomplished by supporting the physician or practitioner/patient relationship and plan of care. P4P initiatives vary more according to the needs and preferences of local providers and plans than do DM initiatives. While DM programs can be implemented without necessarily changing how providers deliver health care, P4P requires new programs and/or systems within the provider sector to improve patient care quality and/or efficiency. P4P initiatives also typically involve the upside or downside risk by physicians/hospitals. Partners HealthCare, based in Boston, features P4P initiatives for inpatient admissions, diabetes, and radiology that have all been met with success. Both DM and P4P initiatives have been successful in managed care. However, in terms of determining whether DM or P4P initiatives are more effective in improving the quality and efficiency of health care delivery, it is simply too early to tell at this time.

  3. First Reports of Human Rotavirus G8P[4] Gastroenteritis in the United States

    Science.gov (United States)

    Payne, Daniel C.; Teel, Elizabeth N.; Mijatovic-Rustempasic, Slavica; Bowen, Michael D.; Wikswo, Mary; Gentsch, Jon R.; Parashar, Umesh D.

    2012-01-01

    In 2009, three children were hospitalized in Rochester, NY, with sequence-confirmed G8P[4] rotavirus gastroenteritis—the first U.S. detection of this uncommon strain more typically found in Africa. Continued monitoring of G8P[4] and other rotavirus genotypes not represented in current vaccines is essential to assess whether vaccination will result in an increase in prevalence of these strains. PMID:22170918

  4. Molecular Cloning and Characterization of P4 Nuclease from Leishmania infantum

    Directory of Open Access Journals (Sweden)

    Safar Farajnia

    2011-01-01

    Full Text Available Parasite of the genus Leishmania is reliant on the salvage pathway for recycling of ribonucleotides. A class I nuclease enzyme also known as P4 nuclease is involved in salvage of purines in cutaneous Leishmania species but the relevant enzymes have not been characterized in Leishmania infantum (L. infantum. The aim of this study was to clone and characterize the gene encoding class I nuclease in L. infantum. DNA extracted from L. infantum was used for amplification of P4 nuclease gene (Li-P4 by PCR. The product was cloned, sequenced, and expressed in E. coli for further characterization. Analysis of the sequence of Li-P4 revealed that the gene consists of an ORF of 951 bp. Sequence similarity analysis indicated that Li-P4 has a high homology to relevant enzymes of other kintoplastids with the highest homology (88% to p1/s1 class I nuclease from L. donovani. Western blotting of antirecombinant Li-P4 with promastigote and amastigote stages of L. infantum showed that this nuclease is present in both stages of parasite with higher expression in amastigote stage. The highly conserved nature of this essential enzyme in Leishmania parasites suggests it as a promising drug target for leishmaniasis.

  5. Crystal structure and energy band and optical properties of phosphate Sr3P4O13

    International Nuclear Information System (INIS)

    Zhang, Y.-C.; Cheng, W.-D.; Wu, D.-S.; Zhang, H.; Chen, D.-G.; Gong, Y.-J.; Kan, Z.-G.

    2004-01-01

    A single crystal of the compound Sr 3 P 4 O 13 has been found and the crystal structure has been characterized by means of single crystal X-ray diffraction analysis. The compound crystallizes in triclinic system and belongs to space group P1-bar. It builds up from SrO 7 polyhedra and P 4 O 13 -6 anions and has a layered structure, and the Sr atoms are located in the interlayer space. The absorption and luminescence spectrum of Sr 3 P 4 O 13 microcrystals have been measured. The calculated results of crystal energy band structure by the DFT show that the solid state of Sr 3 P 4 O 13 is an isolator with direct band gap. The calculated total and partial density of states indicate that the top valence bands are contributions from P 3p and O 2p states and low conduction bands mostly originate from Sr atomic states. The calculated optical response functions expect that the Sr 3 P 4 O 13 is a low refractive index, and it is possible that the Sr 3 P 4 O 13 is used to make transparent material between the UV and FR light zone

  6. Proceedings of the ANS/ASME/NRC international topical meeting on nuclear reactor thermal-hydraulics: LMFBR and HTGR advanced reactor concepts and analysis methods

    International Nuclear Information System (INIS)

    1980-01-01

    Separate abstracts are included for each of the papers presented concerning the thermal-hydraulics of LMFBR type reactors; mathematical methods in nuclear reactor thermal-hydraulics; heat transfer in gas-cooled reactors; and thermal-hydraulics of pebble-bed reactors. Two papers have been previously abstracted and input to the data base

  7. Whole-genome analyses of DS-1-like human G2P[4] and G8P[4] rotavirus strains from Eastern, Western and Southern Africa.

    Science.gov (United States)

    Nyaga, Martin M; Stucker, Karla M; Esona, Mathew D; Jere, Khuzwayo C; Mwinyi, Bakari; Shonhai, Annie; Tsolenyanu, Enyonam; Mulindwa, Augustine; Chibumbya, Julia N; Adolfine, Hokororo; Halpin, Rebecca A; Roy, Sunando; Stockwell, Timothy B; Berejena, Chipo; Seheri, Mapaseka L; Mwenda, Jason M; Steele, A Duncan; Wentworth, David E; Mphahlele, M Jeffrey

    2014-10-01

    Group A rotaviruses (RVAs) with distinct G and P genotype combinations have been reported globally. We report the genome composition and possible origin of seven G8P[4] and five G2P[4] human RVA strains based on the genetic evolution of all 11 genome segments at the nucleotide level. Twelve RVA ELISA positive stool samples collected in the representative countries of Eastern, Southern and West Africa during the 2007-2012 surveillance seasons were subjected to sequencing using the Ion Torrent PGM and Illumina MiSeq platforms. A reference-based assembly was performed using CLC Bio's clc_ref_assemble_long program, and full-genome consensus sequences were obtained. With the exception of the neutralising antigen, VP7, all study strains exhibited the DS-1-like genome constellation (P[4]-I2-R2-C2-M2-A2-N2-T2-E2-H2) and clustered phylogenetically with reference strains having a DS-1-like genetic backbone. Comparison of the nucleotide and amino acid sequences with selected global cognate genome segments revealed nucleotide and amino acid sequence identities of 81.7-100 % and 90.6-100 %, respectively, with NSP4 gene segment showing the most diversity among the strains. Bayesian analyses of all gene sequences to estimate the time of divergence of the lineage indicated that divergence times ranged from 16 to 44 years, except for the NSP4 gene where the lineage seemed to arise in the more distant past at an estimated 203 years ago. However, the long-term effects of changes found within the NSP4 genome segment should be further explored, and thus we recommend continued whole-genome analyses from larger sample sets to determine the evolutionary mechanisms of the DS-1-like strains collected in Africa.

  8. Measurement of K-sub(p) 4.2 GeV/c interactions with a PEPR Vertex Guidance System

    International Nuclear Information System (INIS)

    Schouten, T.E.

    1977-01-01

    For the K - sub(p) 4.2 GeV/c experiment more than three million bubble chamber pictures were taken and analyzed by a collaboration of laboratories in CERN, Amsterdam, Oxford and Nijmegen. The analysis of such a large amount of pictures requires a large degree of automatization in the processing chain. In this thesis a description is presented of the hardware and software of a pattern recognition system for the automatic measurement of bubble chamber pictures: the PEPR Vertex Guidance system. PEPR stands for Precision Encoding and Pattern Recognition. The results of this system are analyzed in terms of speed, throughput, accuracy and efficiency of the measurements

  9. Photon cascade luminescence from Pr3+ ions in LiPrP4O12 polyphosphate

    International Nuclear Information System (INIS)

    Shalapska, T; Stryganyuk, G; Romanyshyn, Yu; Demchenko, P; Voloshinovskii, A; Trots, D; Gektin, A; Dorenbos, P

    2010-01-01

    The spectral-kinetic properties of luminescence from LiY 1-x Pr x P 4 O 12 (x = 1, 0.1) phosphors are studied in the 10-300 K temperature range upon excitation within the UV-VUV spectral range. The luminescence observed for LiPrP 4 O 12 at low temperatures is attributed to both intra-configurational 4f 2 → 4f 2 and inter-configurational 4f5d → 4f 2 radiative transitions of Pr 3+ . The temperature dependence of emission and the decay kinetics of Pr 3+ luminescence from LiY 1-x Pr x P 4 O 12 (x = 1, 0.1) phosphors are explained by temperature stimulated transitions from the 1 S 0 to the Pr 3+ 4f5d state. At low temperatures, the energy potential barrier between the 1 S 0 and 4f5d states is 0.014 eV for LiPrP 4 O 12 . The spectral overlap of the 1 S 0 and 4f5d states of Pr 3+ in LiY 0.9 Pr 0.1 P 4 O 12 determines the luminescence properties in the entire temperature range studied.

  10. Aromatic organic contaminant removal from an aqueous environment by p(4-VP)-based materials.

    Science.gov (United States)

    Sahiner, Nurettin; Ozay, Ozgur; Aktas, Nahit

    2011-10-01

    p(4-vinylpyridine) (p(4-VP)) hydrogels were prepared in bulk (macro, 5 × 6 mm) and in nanosizes (370 nm) dimensions. The prepared hydrogels were used to remove organic aromatic contaminates such as 4-nitrophenol (4-NP), 2-nitrophenol (2-NP), phenol (Ph) and nitrobenzene (NB) from an aqueous environment. Important parameters affecting the absorption phenomena, such as the initial concentration of the organic species and the absorbent, absorption rate, absorption capacity, pH and the temperature of the medium, were evaluated for both hydrogel sizes. The absorption capacity of bulk and microgels were found to be 4-NP>2-NP>Ph>NB. Furthermore, p(4-VP) microgels were embedded in poly(acrylamide) (p(AAm)) bulk hydrogel as a microgel-hydrogel interpenetrating polymer network and proved to be very practical in overcoming the difficulty of using the microgels in real applications. Moreover, it was demonstrated that separately prepared magnetic ferrite particles inserted inside p(4-VP) microgels during synthesis allowed for trouble-free removal of p(4-VP)-magnetic composite microgels from the aqueous environment by an externally applied magnetic field upon completion of their task. Copyright © 2011 Elsevier Ltd. All rights reserved.

  11. P(4-VP) based nanoparticles and composites with dual action as antimicrobial materials.

    Science.gov (United States)

    Ozay, Ozgur; Akcali, Alper; Otkun, Müşerref Tatman; Silan, Coskun; Aktas, Nahit; Sahiner, Nurettin

    2010-09-01

    Polymeric 4-VP (p(4-VP)) particles were synthesized in an oil-in-water microemulsion system using various amounts of ethylene glycol dimethacrylate (EGDMA) as crosslinker. The prepared p(4-VP) particles were chemically modified to obtain positively charged particles as polyelectrolytes. Furthermore, these p(4-VP) particles were used for in situ Ag and Cu metal nanoparticle syntheses to provide dual action with an additional advantage as bactericidal particles. The synthesized p(4-VP) particles with positive charges and metal constituents were tested for potential antibacterial action against various bacteria such as Staphylococcus aureus ATCC6538, Pseudomonas aeruginosa ATCC9027, Bacillus subtilis ATCC6633, Escherichia coli ATCC8739. It was found that p(4-VP) particles, especially the positively charged forms had potential as antibacterial materials. The synthesized particle dimensions were characterized with TEM, and DLS measurements. Chemical modification of the particles was confirmed by FT-IR spectroscopy and zeta potential measurements, and the metal nanoparticle contents were determined with thermogravimetric (TGA) studies. Copyright 2010 Elsevier B.V. All rights reserved.

  12. Summary of treat experiments on oxide core-disruptive accidents

    International Nuclear Information System (INIS)

    Dickerman, C.E.; Rothman, A.B.; Klickman, A.E.; Spencer, B.W.; DeVolpi, A.

    1979-02-01

    A program of transient in-reactor experiments is being conducted by Argonne National Laboratory in the Transient Reactor Test (TREAT) facility to guide and support analyses of hypothetical core-disruptive accidents (HCDA) in liquid-metal fast breeder reactors (LMFBR). Test results provide data needed to establish the response of LMFBR cores to hypothetical accidents producing fuel failure, coolant boiling, and the movement of coolant, molten fuel, and molten cladding. These data include margins to fuel failure, the modes of failure and movements, and evidence for identification of the mechanisms which determine the failure and movements. A key element in the program is the fast-neutron hodoscope, which detects fuel movement as a function of time during experiments

  13. Cleavage leads to expansion of bacteriophage P4 procapsids in vitro

    International Nuclear Information System (INIS)

    Wang Sifang; Chandramouli, Preethi; Butcher, Sarah; Dokland, Terje

    2003-01-01

    Proteolytic cleavage of the structural proteins is an important part of the maturation process for most bacteriophages and other viruses. In the double-stranded DNA bacteriophages this cleavage is associated with DNA packaging, capsid expansion, and scaffold removal. To understand the role of protein cleavage in the expansion of bacteriophages P2 and P4, we have experimentally cleaved P4 procapsids produced by overexpression of the capsid and scaffolding proteins. The cleavage leads to particle expansion and scaffold removal in vitro. The resulting expanded capsid has a thin-shelled structure similar, but not identical, to that of mature virions

  14. Biochemical Characterization of P4-ATPase Mutations Associated with Intrahepatic Cholestatic Disease

    DEFF Research Database (Denmark)

    Gantzel, Rasmus; Vestergaard, Anna Lindeløv; Mikkelsen, Stine

    The cholestatic disorders progressive familial intrahepatic cholestasis type 1 (PFIC1, also referred to as Byler’s disease) and benign recurrent intrahepatic cholestasis type 1 (BRIC1) are caused by mutation of the P4-ATPase ATP8B1. The substrate of ATP8B1 is very likely to be phosphatidylserine ...... in the transmembrane domain will contribute with important information in elucidation of the phospholipid transport mechanism of P4-type ATPases. 1. Folmer, D.E., R.P.J. Oude Elferink, and C.C. Paulusma, Biochim. Biophys. Acta (2009) 1791. 628-635....

  15. Permitting patients to pay for participation in clinical trials: the advent of the P4 trial.

    Science.gov (United States)

    Shaw, David; de Wert, Guido; Dondorp, Wybo; Townend, David; Bos, Gerard; van Gelder, Michel

    2017-06-01

    In this article we explore the ethical issues raised by permitting patients to pay for participation (P4) in clinical trials, and discuss whether there are any categorical objections to this practice. We address key considerations concerning payment for participation in trials, including patient autonomy, risk/benefit and justice, taking account of two previous critiques of the ethics of P4. We conclude that such trials could be ethical under certain strict conditions, but only if other potential sources of funding have first been explored or are unavailable.

  16. Detection of marine aerosols with IRS P4-Ocean Colour Monitor

    Indian Academy of Sciences (India)

    R.Narasimhan(krishtel emaging) 1461 1996 Oct 15 13:05:22

    Sensing Satellite IRS P4-OCM (Ocean Colour Monitor) can be used for deriving aerosol optical depth (AOD) over the oceans. A retrieval ... effect can offset the greenhouse forcing by about. 20–40% [WMO 1996; Penner et al (IPCC) ... soon by reducing the land-sea temperature con- trast (Galindo 1984; Kaufman et al 1997), ...

  17. Estimation of surface Latent Heat Fluxes from IRS-P4/MSMR ...

    Indian Academy of Sciences (India)

    The brightness temperatures of the Microwave sensor MSMR (Multichannel Scanning Microwave Radiometer) launched in May 1999 onboard Indian Oceansat-1 IRS-P4 are used to develop a direct retrieval method for latent heat ux by multivariate regression technique. The MSMR measures the microwave radiances at 8 ...

  18. Proper depiction of monsoon depression through IRS-P4 MSMR

    Indian Academy of Sciences (India)

    R. Narasimhan (Krishtel eMaging) 1461 1996 Oct 15 13:05:22

    analyzed for the complete life cycle of monsoon depression. Geophysical parameters ... This indicated the possibility of increase in cyclonic vorticity ..... wal R K 2002 Assimilation of IRS-P4 (MSMR) meteoro- logical data in the NCMRWF global data assimilation system; Proc. Indian Aca. Sci. (Earth Planet. Sci.) 111. 351–364.

  19. 77 FR 26014 - Prospective Grant of Exclusive License: P4 Peptide From Streptococcus Pneumoniae

    Science.gov (United States)

    2012-05-02

    ... Licensing and Marketing Specialist, Technology Transfer Office, Centers for Disease Control and Prevention... Grant of Exclusive License: P4 Peptide From Streptococcus Pneumoniae AGENCY: Technology Transfer Office... for Disease Control and Prevention (CDC), Technology Transfer Office, Department of Health and Human...

  20. Chitinase production and antifungal potential of endophytic Streptomyces strain P4

    Directory of Open Access Journals (Sweden)

    Hataichanoke Niamsup

    2012-02-01

    Full Text Available The endophytic actinomycete P4 strain, previously isolated from sweet pea root, wasidentified as Streptomyces sp. by full 16S rRNA sequencing. It is mostly related to Streptomycesgriseoflavus with a 99.7% identity score. The Streptomyces sp. P4 was tested for its hydrolyticactivities by plate method. The result showed the presence of chitinase. The extent of chitinase activitywas assessed by spectrophotometric method along with growth monitoring. Chitinase production wasgrowth-associated and showed the highest activity on the fifth day. The dual culture method revealedthat the strain was effective in restricting the radial growth of Fusarium oxysporum f.sp. lycopersici, animportant phytopathogen of tomato. Scanning electronic microscopic analysis showed that the ruptureof the F. oxysporum mycelial cell wall occurred at the area of interaction between F. oxysporum andStreptomyces sp. P4. This was possibly due to the chitinolytic activity of the P4. Thus, thisactinomycete has the potential for being used as a biocontrol agent, thereby reducing the use ofchemical fungicides.

  1. Estimation of surface latent heat fluxes from IRS-P4/MSMR satellite ...

    Indian Academy of Sciences (India)

    The brightness temperatures of the Microwave sensor MSMR (Multichannel Scanning Microwave Radiometer) launched in May 1999 onboard Indian Oceansat-1 IRS-P4 are used to develop a direct retrieval method for latent heat ux by multivariate regression technique. The MSMR measures the microwave radiances at 8 ...

  2. The Luteovirus P4 Movement Protein Is a Suppressor of Systemic RNA Silencing.

    Science.gov (United States)

    Fusaro, Adriana F; Barton, Deborah A; Nakasugi, Kenlee; Jackson, Craig; Kalischuk, Melanie L; Kawchuk, Lawrence M; Vaslin, Maite F S; Correa, Regis L; Waterhouse, Peter M

    2017-10-10

    The plant viral family Luteoviridae is divided into three genera: Luteovirus , Polerovirus and Enamovirus . Without assistance from another virus, members of the family are confined to the cells of the host plant's vascular system. The first open reading frame (ORF) of poleroviruses and enamoviruses encodes P0 proteins which act as silencing suppressor proteins (VSRs) against the plant's viral defense-mediating RNA silencing machinery. Luteoviruses, such as barley yellow dwarf virus-PAV (BYDV-PAV), however, have no P0 to carry out the VSR role, so we investigated whether other proteins or RNAs encoded by BYDV-PAV confer protection against the plant's silencing machinery. Deep-sequencing of small RNAs from plants infected with BYDV-PAV revealed that the virus is subjected to RNA silencing in the phloem tissues and there was no evidence of protection afforded by a possible decoy effect of the highly abundant subgenomic RNA3. However, analysis of VSR activity among the BYDV-PAV ORFs revealed systemic silencing suppression by the P4 movement protein, and a similar, but weaker, activity by P6. The closely related BYDV-PAS P4, but not the polerovirus potato leafroll virus P4, also displayed systemic VSR activity. Both luteovirus and the polerovirus P4 proteins also showed transient, weak local silencing suppression. This suggests that systemic silencing suppression is the principal mechanism by which the luteoviruses BYDV-PAV and BYDV-PAS minimize the effects of the plant's anti-viral defense.

  3. Design of a new hairpin DNAzyme: The activity controlled by TMPyP4

    African Journals Online (AJOL)

    Jane

    2011-08-01

    . The formation and stability of the G-quadruplex structure as the DNAzyme stem in the absence or the presence of TMPyP4 ..... presence of 100 nM 32P-labeled RNA substrate as indicated, the reaction product was visualized ...

  4. Analysis of marine aerosol optical depth retrieved from IRS-P4 OCM ...

    Indian Academy of Sciences (India)

    Aerosol optical depth is regularly derived from SeaWiFS and MODIS sensor and used by the sci- entific community in various climatic studies. In the present study an attempt has been made to retrieve the aerosol optical depth using the IRS-P4 OCM sensor data and a comparison has been carried out using few ...

  5. Detection of marine aerosols with IRS P4-Ocean Colour Monitor

    Indian Academy of Sciences (India)

    The atmospheric correction bands 7 and 8 (765nm and 865nm respectively) of the Indian Remote Sensing Satellite IRS P4-OCM (Ocean Colour Monitor) can be used for deriving aerosol optical depth (AOD) over the oceans. A retrieval algorithm has been developed which computes the AOD using band 7 data by treating ...

  6. The plant P4-ATPase ALA2 is involved in flipping of phosphatidylserine analogues

    DEFF Research Database (Denmark)

    Lopez Marques, Rosa Laura

    The plant P4-ATPase ALA2 is involved in flipping of phosphatidylserine analogues Rosa Laura López-Marqués1, Lisbeth Rosager Poulsen1, Katharina Meffert2, Thomas Pomorski2, Michael Gjedde Palmgren1 1Centre for Membrane Pumps in Cells and Disease - PUMPKIN, Danish National Research Foundation...

  7. P4-ATPases on the spotlight: lessons from a green world

    DEFF Research Database (Denmark)

    Lopez Marques, Rosa Laura

    flippases, play an essential role in this transport process. We have recently characterized several members of the P4 subfamily of P-type ATPases as prime candidate lipid flippases in the secretory pathway of several eukaryotic cells. Our studies in yeast, plants and mammalian cells uncovered...

  8. Overexpression and purification of the primase domain of bacteriophage P4 gp alpha for structure determination by NMR

    NARCIS (Netherlands)

    de Planque, M.R.R.; Ziegelin, G.; Lanka, E.; Boelens, R.

    2003-01-01

    Bacteriophage P4 is a temperate phage of E. coli and other Gram-negative prokaryotes. Its alpha gene encodes a 777-residue multifunctional protein, gpa, that is essential and sufficient for the initiation of P4 DNA replication. The gpa protein attaches to the P4 origin of replication, unwinds the

  9. The plant P4-ATPase ALA2 is involved in flipping of phosphatidylserine analogues

    DEFF Research Database (Denmark)

    Lopez Marques, Rosa Laura

    The plant P4-ATPase ALA2 is involved in flipping of phosphatidylserine analogues Rosa Laura López-Marqués1, Lisbeth Rosager Poulsen1, Katharina Meffert2, Thomas Pomorski2, Michael Gjedde Palmgren1 1Centre for Membrane Pumps in Cells and Disease - PUMPKIN, Danish National Research Foundation......, Department of Plant Biology and Biotechnology, University of Copenhagen, DK-1871 Frederiksberg C, Denmark 2Humboldt-University Berlin, Faculty of Mathematics and Natural Science I, Institute of Biology, 10115 Berlin, Germany In the model plant Arabidopsis thaliana 12 P4-ATPases are present, named ALA1 to 12...... by lack of DRS2 in yeast. Tissue specific expression patterns of ALA2 and ALIS genes indicate that different ALIS isoforms may interact with ALA2 in diverse parts of the plant. At present we are studying the subcellular localization of ALA2 in planta in order to understand better its possible...

  10. The plant P4-ATPase ALA2 is involved in flipping of phosphatidylserine analogues

    DEFF Research Database (Denmark)

    Poulsen, Lisbeth Rosager

      The plant P4-ATPase ALA2 is involved in flipping of phosphatidylserine analogues Rosa Laura López-Marqués1, Lisbeth Rosager Poulsen1, Katharina Meffert2, Thomas Pomorski2, Michael Gjedde Palmgren1 1Centre for Membrane Pumps in Cells and Disease - PUMPKIN, Danish National Research Foundation......, Department of Plant Biology and Biotechnology, University of Copenhagen, DK-1871 Frederiksberg C, Denmark 2Humboldt-University Berlin, Faculty of Mathematics and Natural Science I, Institute of Biology, 10115 Berlin, Germany In the model plant Arabidopsis thaliana 12 P4-ATPases are present, named ALA1 to 12...... by lack of DRS2 in yeast. Tissue specific expression patterns of ALA2 and ALIS genes indicate that different ALIS isoforms may interact with ALA2 in diverse parts of the plant. At present we are studying the subcellular localization of ALA2 in planta in order to understand better its possible...

  11. Monte-Carlo Modeling of Parameters of a Subcritical Cascade Reactor Based on MSBR and LMFBR Technologies

    CERN Document Server

    Bznuni, S A; Zhamkochyan, V M; Polanski, A; Sosnin, A N; Khudaverdyan, A H

    2001-01-01

    Parameters of a subcritical cascade reactor driven by a proton accelerator and based on a primary lead-bismuth target, main reactor constructed analogously to the molten salt breeder (MSBR) reactor core and a booster-reactor analogous to the core of the BN-350 liquid metal cooled fast breeder reactor (LMFBR). It is shown by means of Monte-Carlo modeling that the reactor under study provides safe operation modes (k_{eff}=0.94-0.98), is apable to transmute effectively radioactive nuclear waste and reduces by an order of magnitude the requirements on the accelerator beam current. Calculations show that the maximal neutron flux in the thermal zone is 10^{14} cm^{12}\\cdot s^_{-1}, in the fast booster zone is 5.12\\cdot10^{15} cm^{12}\\cdot s{-1} at k_{eff}=0.98 and proton beam current I=2.1 mA.

  12. CRAB-II: a computer program to predict hydraulics and scram dynamics of LMFBR control assemblies and its validation

    International Nuclear Information System (INIS)

    Carelli, M.D.; Baker, L.A.; Willis, J.M.; Engel, F.C.; Nee, D.Y.

    1982-01-01

    This paper presents an analytical method, the computer code CRAB-II, which calculates the hydraulics and scram dynamics of LMFBR control assemblies of the rod bundle type and its validation against prototypic data obtained for the Clinch River Breeder Reactor (CRBR) primary control assemblies. The physical-mathematical model of the code is presented, followed by a description of the testing of prototypic CRBR control assemblies in water and sodium to characterize, respectively, their hydraulic and scram dynamics behavior. Comparison of code predictions against the experimental data are presened in detail; excellent agreement was found. Also reported are experimental data and empirical correlations for the friction factor of the absorber bundle in the entire flow range (laminar to turbulent) which represent an extension of the state-of-the-art, since only fuel and blanket assemblies friction factor correlations were previously reported in the open literature

  13. FMEF profilometry and visual examination feasibility and conceptual design. [Fuels and Materials Examination Facility; LMFBR and GCFR

    Energy Technology Data Exchange (ETDEWEB)

    Philipp, L.D.; Dilbeck, R.A.; Hartman, J.S.; Hildebrand, B.P.; Reich, F.R.; Swinth, K.L.

    1976-07-01

    The Fuels and Materials Examination Facility (FMEF) is being scoped to provide postirradiation examination capabilities for FFTF, LMFBR and GCFR fuels and materials. The Hanford Engineering Development Laboratory has requested that the Battelle Pacific Northwest Laboratory (PNL) complete a feasibility study for the development of equipment to meet the FMEF Measurement Requirements for irradiated fuel pin and absorber rod bow, length, profile and visual examination stations. The purpose of the report is to provide a conceptual design for development of the examination equipment. The design analysis assumes that fuel pins and absorber rods to be examined are in the main cell. The cell's environment will be argon or nitrogen gas at a pressure between --1 and --4 in. of water and at a temperature between 70 and 100/sup 0/F. Oxygen content of the cell gas will normally be controlled between 25 and 50 ppM. Water content will be controlled within the same limits.

  14. Ab Initio calculation of the vibrational spectrum and thermodynamic properties of rhombohedral P4O10

    OpenAIRE

    Rustad, James R.

    2011-01-01

    Plane-wave pseudopotential methods and density functional perturbation theory are used to calculate the phonon density of states and thermodynamic functions of h-P4O10. The calculated vibrational spectrum is in good agreement with the measured spectrum, but the calculations indicate some modifications in the interpretation of the spectrum, mainly suggesting changes in the number of components used to fit a few of the observed peaks. The calculated low-temperature heat capacity is in good agre...

  15. The Luteovirus P4 Movement Protein Is a Suppressor of Systemic RNA Silencing

    Directory of Open Access Journals (Sweden)

    Adriana F. Fusaro

    2017-10-01

    Full Text Available The plant viral family Luteoviridae is divided into three genera: Luteovirus, Polerovirus and Enamovirus. Without assistance from another virus, members of the family are confined to the cells of the host plant’s vascular system. The first open reading frame (ORF of poleroviruses and enamoviruses encodes P0 proteins which act as silencing suppressor proteins (VSRs against the plant’s viral defense-mediating RNA silencing machinery. Luteoviruses, such as barley yellow dwarf virus-PAV (BYDV-PAV, however, have no P0 to carry out the VSR role, so we investigated whether other proteins or RNAs encoded by BYDV-PAV confer protection against the plant’s silencing machinery. Deep-sequencing of small RNAs from plants infected with BYDV-PAV revealed that the virus is subjected to RNA silencing in the phloem tissues and there was no evidence of protection afforded by a possible decoy effect of the highly abundant subgenomic RNA3. However, analysis of VSR activity among the BYDV-PAV ORFs revealed systemic silencing suppression by the P4 movement protein, and a similar, but weaker, activity by P6. The closely related BYDV-PAS P4, but not the polerovirus potato leafroll virus P4, also displayed systemic VSR activity. Both luteovirus and the polerovirus P4 proteins also showed transient, weak local silencing suppression. This suggests that systemic silencing suppression is the principal mechanism by which the luteoviruses BYDV-PAV and BYDV-PAS minimize the effects of the plant’s anti-viral defense.

  16. Commercial liquid-metal MHD conversion systems coupled to LMFBR and coal-fired fluidized bed combustors

    International Nuclear Information System (INIS)

    Amend, W.E.; Brunsvold, A.; Pierson, E.S.

    1975-01-01

    The constraints imposed on two-phase liquid-metal MHD (LMMHD) when employed in commercial power plants with practical heat sources have not previously been studied. The coupling of a LMMHD power system with an LMFBR and a coal-fired fluidized bed combustor are considered. Two MHD systems are considered. The first is a dual cycle where heat is added to both the liquid metal and the gas, and the gas may expand through a gas turbine after the MHD generator. The second system, a binary cycle, differs in that a significant portion of the sensible heat in the gas entering the compression loop is converted to useful power in a steam bottoming cycle. The effect of liquid-metal vapor carry-over into the gas loop is included. The couplings of the LMMHD system with the heat sources and with the steam plants were studied in depth. The results of the study of each interface are presented parametrically for each heat source and energy conversion system. Operating points have been selected and the complete schematic of each system considered is presented along with all thermodynamic state points and fluid flow rates. All system parameters and component efficiencies were selected to be consistent with near term technology and good engineering design principles. These criteria yielded a system performance of 37 percent for an LMFBR operating with a maximum reactor coolant temperature of 1200 0 F when the pure LMMHD energy converter was used. A LMMHD/steam binary cycle is shown to be capable of achieving a thermal efficiency of 44.8 percent when used with the same heat source. Results with the coal fluidized bed combustor as a heat source show even higher performance levels (about 50 percent efficiency) since the maximum cycle temperature is increased

  17. Signatures of rocky planet engulfment in HAT-P-4. Implications for chemical tagging studies

    Science.gov (United States)

    Saffe, C.; Jofré, E.; Martioli, E.; Flores, M.; Petrucci, R.; Jaque Arancibia, M.

    2017-07-01

    Aims: We aim to explore the possible chemical signature of planet formation in the binary system HAT-P-4 by studying the trends of abundance vs. condensation temperature Tc. The star HAT-P-4 hosts a planet detected by transits, while its stellar companion does not have any detected planet. We also study the lithium content, which might shed light on the problem of Li depletion in exoplanet host stars. Methods: We derived for the first time both stellar parameters and high-precision chemical abundances by applying a line-by-line full differential approach. The stellar parameters were determined by imposing ionization and excitation equilibrium of Fe lines, with an updated version of the FUNDPAR program, together with ATLAS9 model atmospheres and the MOOG code. We derived detailed abundances of different species with equivalent widths and spectral synthesis with the MOOG program. Results: The exoplanet host star HAT-P-4 is found to be 0.1 dex more metal rich than its companion, which is one of the highest differences in metallicity observed in similar systems. This could have important implications for chemical tagging studies. We rule out a possible peculiar composition for each star, such as is the case for λ Boötis and δ Scuti, and neither is this binary a blue straggler. The star HAT-P-4 is enhanced in refractory elements relative to volatile when compared to its stellar companion. Notably, the Li abundance in HAT-P-4 is greater than that of its companion by 0.3 dex, which is contrary to the model that explains the Li depletion by the presence of planets. We propose a scenario where at the time of planet formation, the star HAT-P-4 locked the inner refractory material in planetesimals and rocky planets, and formed the outer gas giant planet at a greater distance. The refractories were then accreted onto the star, possibly as a result of the migration of the giant planet. This explains the higher metallicity, the higher Li content, and the negative Tc trend we

  18. SAS4A simulation of the OPERA-15 two-dimensional voiding experiment

    International Nuclear Information System (INIS)

    Briggs, L.L.

    1984-01-01

    A major effort is currently being pursued to validate the SAS4A LMFBR accident analysis code. Part of this effort involves SAS4A analysis of both in-pile and out-of-pile safety experiments. Such an experiment is the fifteen-pin Out-of-Pile Explusion and Reentry Apparatus (OPERA) test run at Argonne National Laboratory. This test uses a fifteen-pin triangular-shaped bundle of simulant fuel pins to demonstrate two-dimensional voiding behavior in a LMFBR subassembly during a Loss-of-Flow (LOF) accident. This experiment was chosen for SAS4A analysis both for its value in code validation and its usefulness in evaluating the limitations of the one-dimensional SAS4A sodium voiding model in accident analysis

  19. Influence of strain rate and temperature on the yield and fracture toughness behavior of selected steels for an LMFBR spent fuel shipping cask, a literature assessment

    International Nuclear Information System (INIS)

    Rack, H.J.

    1976-02-01

    The literature has been reviewed to determine the possible influences of strain rate and temperature on the yield and fracture toughness behavior of selected steels suggested for use in an LMFBR Spent Fuel Shipping Cask. Based on this information, recommendations have been made for further work which is intended to alleviate potential problems prior to their having a major impact on the shipping cask program

  20. Computational analysis of coolant mixing in subassembly and hot pool of an LMFBR

    International Nuclear Information System (INIS)

    Natesan, K.; Velusamy, K.; Kasinathan, N.; Clement Ravichandar, S.; Selvaraj, P.; Ghosh, D.; Chellapandi, P.; Chetal, S.C.

    2005-01-01

    Full text of publication follows: The reactor core of a typical Liquid Metal cooled Fast Breeder Reactor (LMFBR) comprises of several fuel, blanket, storage, reflector and shielding subassemblies (SA) arranged in a hexagonal geometry. Each fuel subassembly (FSA) comprises of 217 fuel pins packed with pellets of fissile and fertile materials. The wire wrapped pins are arranged in triangular pitch within a hexagonal wrapper. Due to the non uniform flow resistance across the cross section, sodium velocity is non uniform within SA. This non uniform velocity distribution coupled with radial power profile causes the sodium coolant to come out of the pin bundles of SA with a non uniform temperature profile. From the fuel pin bundle top, sodium flows axially through various regions comprising of a sodium plenum, shielding bundle region and SA head and adapter assembly. These regions contribute in the mixing of sodium in SA. Due to the non uniform temperature distribution at FSA top, the temperature profile at the possible locations of core monitoring thermocouple (TC) would also be non uniform. During a power campaign of core, FSA top drift outwards with respect to TC location due to irradiation bowing. This causes the temperature recorded by the TC to change in accordance with the temperature of sodium stream washing it from time to time during the power campaign. Apart from this, the non uniform temperature at the FSA exits can also lead to fluctuation in the temperature of sodium at TC locations. Knowledge of these phenomena in hot pool is essential in fixing the SCRAM threshold on the parameters that are derived from the measurements made by these TC. Analyses to study the above phenomena have been carried out in three stages. In the first stage, velocity and temperature distributions in the wire wrap bundle region of FSA have been obtained through subchannel analysis using the SUPER ENERGY code. In the second stage, 3D mixing of sodium in FSA in the region above the

  1. Basic analysis and a comparison of the characteristics GCFRs and the LMFBR with the thorium cycle in one-group diffusion theory

    International Nuclear Information System (INIS)

    Sabundjian, G.; Ishiguro, Y.

    1991-09-01

    A preliminary study of neutronics of thorium cycle fast breeder reactor has been done using simplified reactor models and analyses methods with the aim of finding a type of breeder reactor suitable for an efficient utilization of thorium that is abundant in Brazil. Basic methods of cross section processing and reactor calculation are studied and applied to analyse breeding characteristics of GCFRs and LMFBRs. The GCFR is fueled with oxide pins and cooled with helium. The LMFBR is fueled with thin metallic pins to achieve high power densities. Neutronics characteristics are determined as functions of the average power density and the fuel volume fraction. Results show that a high power density and a high fuel volume fraction are desirable to achieve short doubling times, that the GCFR is inferior to the LMFBR in regard to the doubling time and that the LMFBR can achieve reactor doubling times ten years with an average power density of ∼ 600MW/m 3 and fuel volume fraction of 40%. (author)

  2. SignalP 4.0 Server - prediction results The deduced signal peptide ...

    Indian Academy of Sciences (India)

    15136770661wry

    SignalP 4.0 Server - prediction results. The deduced signal peptide data of MaSox4. Measure Position Value. Cutoff signal peptide? max. C. 40. 0.125 max. Y. 40. 0.111 max. S. 39. 0.117 mean S. 1-39. 0.097. D. 1-39. 0.103 0.450 NO. Name=Sequence SP='NO' D=0.103 D-cutoff=0.450 Networks=SignalP-noTM. Name= ...

  3. From systems biology to P4 medicine: applications in respiratory medicine

    Directory of Open Access Journals (Sweden)

    Guillaume Noell

    2018-02-01

    Full Text Available Human health and disease are emergent properties of a complex, nonlinear, dynamic multilevel biological system: the human body. Systems biology is a comprehensive research strategy that has the potential to understand these emergent properties holistically. It stems from advancements in medical diagnostics, “omics” data and bioinformatic computing power. It paves the way forward towards “P4 medicine” (predictive, preventive, personalised and participatory, which seeks to better intervene preventively to preserve health or therapeutically to cure diseases. In this review, we: 1 discuss the principles of systems biology; 2 elaborate on how P4 medicine has the potential to shift healthcare from reactive medicine (treatment of illness to predict and prevent illness, in a revolution that will be personalised in nature, probabilistic in essence and participatory driven; 3 review the current state of the art of network (systems medicine in three prevalent respiratory diseases (chronic obstructive pulmonary disease, asthma and lung cancer; and 4 outline current challenges and future goals in the field.

  4. The new holism: P4 systems medicine and the medicalization of health and life itself.

    Science.gov (United States)

    Vogt, Henrik; Hofmann, Bjørn; Getz, Linn

    2016-06-01

    The emerging concept of systems medicine (or 'P4 medicine'-predictive, preventive, personalized and participatory) is at the vanguard of the post-genomic movement towards 'precision medicine'. It is the medical application of systems biology, the biological study of wholes. Of particular interest, P4 systems medicine is currently promised as a revolutionary new biomedical approach that is holistic rather than reductionist. This article analyzes its concept of holism, both with regard to methods and conceptualization of health and disease. Rather than representing a medical holism associated with basic humanistic ideas, we find a technoscientific holism resulting from altered technological and theoretical circumstances in biology. We argue that this holism, which is aimed at disease prevention and health optimization, points towards an expanded form of medicalization, which we call 'holistic medicalization': Each person's whole life process is defined in biomedical, technoscientific terms as quantifiable and controllable and underlain a regime of medical control that is holistic in that it is all-encompassing. It is directed at all levels of functioning, from the molecular to the social, continual throughout life and aimed at managing the whole continuum from cure of disease to optimization of health. We argue that this medicalization is a very concrete materialization of a broader trend in medicine and society, which we call 'the medicalization of health and life itself'. We explicate this holistic medicalization, discuss potential harms and conclude by calling for preventive measures aimed at avoiding eventual harmful effects of overmedicalization in systems medicine (quaternary prevention).

  5. Recommended practices in elevated temperature design: A compendium of breeder reactor experiences (1970-1986): An overview

    International Nuclear Information System (INIS)

    Wei, B.C.; Cooper, W.L. Jr.; Dhalla, A.K.

    1987-09-01

    Significant experiences have been accumulated in the establishment of design methods and criteria applicable to the design of Liquid Metal Fast Breeder Reactor (LMFBR) components. The Subcommittee of the Elevated Temperature Design under the Pressure Vessel Research Council (PVRC) has undertaken to collect, on an international basis, design experience gained, and the lessons learned, to provide guidelines for next generation advanced reactor designs. This paper shall present an overview and describe the highlights of the work

  6. P4HB promotes HCC tumorigenesis through downregulation of GRP78 and subsequent upregulation of epithelial-to-mesenchymal transition.

    Science.gov (United States)

    Xia, Wei; Zhuang, Juhua; Wang, Guoyu; Ni, Jing; Wang, Jiening; Ye, Ying

    2017-01-31

    P4HB and GRP78 are molecular chaperones involved in cellular response to ER stress. They have been linked to cancer progression; however, their roles in hepatocellular carcinoma (HCC) are largely unclear. In this study, we found that P4HB is overexpressed in human HCC tissues and cell lines. Higher tumoral P4HB levels are correlated with more advanced disease and poorer survival. GRP78 expression is inversely correlated with P4HB in human HCC tissues, and downregulated by P4HB in HCC cell lines. P4HB overexpression promotes HCC cell growth, migration, invasion and epithelial-to-mesenchymal transition (EMT) in vitro. GRP78 overexpression not only inhibits HCC cell growth, migration, invasion and EMT, but also antagonizes the oncogenic effects of P4HB overexpression. Furthermore, P4HB silencing inhibits HCC tumorigenesis in vivo. Taken together, our results provided evidence that P4HB promotes HCC progression through downregulation of GRP78 and subsequent upregulation of EMT.

  7. Experiences on removal of sodium-water reaction products in SWAT-3

    International Nuclear Information System (INIS)

    Tanabe, H.; Hiroi, H.; Sato, M.; Otaka, J.

    2002-01-01

    This report summarizes experiences and information concerning the removal of sodium water reaction products (SMRP) obtained through large leak tests of the Steam Generator Safety Test Facility (SWAT-3) at PNC/OEC, which were conducted to validate the safety design of steam generators of a prototype LMFBR Monju. The following three problems are discussed here: (1) drainability of SWRP, (2) removal of SWRP by using a cold trap, and (3) steam cleaning of SWRP. (author)

  8. Biochemical Characterization of P4-ATPase Mutations Associated with Intrahepatic Cholestatic Disease

    DEFF Research Database (Denmark)

    Gantzel, Rasmus; Vestergaard, Anna Lindeløv; Mikkelsen, Stine

    The cholestatic disorders progressive familial intrahepatic cholestasis type 1 (PFIC1) and benign recurrent intrahepatic cholestasis type 1 (BRIC1) are caused by mutation of the P4-ATPase ATP8B1 that flips phospholipid from the exoplasmic leaflet to the cytoplasmic leaflet of canalicular membranes....... It is hypothesized that PFIC1 mutations are generally more disturbing than BRIC1 mutations with respect to expression, structural stability and/or function. Although recent data have indicated that the specific phospholipid substrate of ATP8B1 is phosphatidylcholine (PC) [1] whereas ATP8A2 flips phosphatidylserine...... and the lipid substrate of the mutant proteins. L308F and E897K provide clues to where the lipid substrate might bind and enter the protein. The charge reversal from negative to positive in the E897K increases the affinity for the negatively charged PS significantly, whereas the neutral PE binds with wild type...

  9. Biochemical characterization of P4-ATPase mutations associated with Intrahepatic Cholestatic Disease

    DEFF Research Database (Denmark)

    Gantzel, Rasmus; Vestergaard, Anna Lindeløv; Mikkelsen, Stine

    Progressive familial intrahepatic cholestasis type 1 (PFIC1) and benign recurrent intrahepatic cholestasis type 1 (BRIC1) are caused by mutation of the P4-ATPase ATP8B1 that flips phospholipid from the exoplasmic leaflet to the cytoplasmic leaflet of canalicular membranes. It is hypothesized...... that PFIC1 mutations are the most disturbing with respect to expression, structural stability and/or function. Although recent data indicates that the specific phospholipid substrate of ATP8B1 is phosphatidylcholine (PC) [1] whereas ATP8A2 flips phosphatidylserine (PS) and phosphatidylethanolamine (PE...... the protein. The charge reversal from negative to positive in E897K increases the affinity for the negatively charged PS significantly, whereas the neutral PE binds with wild type-like affinity. The BRIC1 mutant L308F has reduced affinity for both lipids, but almost wild type-like maximal rate and cellular...

  10. The putative α/β-hydrolases of Dietzia cinnamea P4 strain as potential enzymes for biocatalytic applications

    NARCIS (Netherlands)

    Procopio da Silva, Luciano; Macrae, Andrew; van Elsas, Jan Dirk; Seldin, Lucy

    The draft genome of the soil actinomycete Dietzia cinnamea P4 reveals a versatile group of alpha/beta-hydrolase fold enzymes. Phylogenetic and comparative sequence analyses were used to classify the alpha/beta-hydrolases of strain P4 into six different groups: (i) lipases, (ii) esterases, (iii)

  11. CRT code and results of some studies for power, reactivity and temperatures for LMFBR fuel rods under operational transients

    International Nuclear Information System (INIS)

    Om Pal Singh; Ponpondi, S.; Parikh, M.V.

    1985-01-01

    The paper describes the details of the computer code, CRT, that has been developed to study the reactor power, reactivity and temperature transients in LMFBR fuel rods under operational transients. The code is based upon suitable modelling of reactor neutron kinetics, heat transfer phenomena and reactivity feedback effects coming from: axial/radial expansion of the fuel/clad/coolant; core boundary movement to axial and radial blankets; sodium entry/expulsion during the radial expansion of the core and apparent insertion/removal of control rods during core/reactor vessel expansion. Further, the results of some studies like, transient behaviour of reactor power and temperature distribution in fuel rods for reactor at low and high initial powers and for fresh and irradiated fuels; comparison of lumped and exact heat transfer models and evaluation of limiting reactivity addition rates for the lumped model to be adequate; influence of the gap conductance on the temperature distributions inside the fuel pellet and the clad and break up of reactivity coming from different feedback mechanisms and their dependence upon the heat transfer parameters are also presented. (author)

  12. PBDOWN - a computer code for simulating core material discharge and thermal to mechanical energy conversion in LMFBR hypothetical accidents

    International Nuclear Information System (INIS)

    Royl, P.

    1981-01-01

    PBDOWN is a computer code that simulates the blowdown of confined boiling materials ('pools') into a colder upper coolant plenum as time dependent ejection and expansion with consideration of a few selected exchange processes. Its application is restricted to situations resulting from hypothetical loss of flow (LOF) accidents in LMFBR's, where enough voiding has occured, that in core sodium vapor pressures become negligible. PBDOWN considers one working fluid for the discharge process (either fuel or steel) and a maximum of two working fluids (either fuel and sodium or steel and sodium) for the expansion process in the upper coolant plenum. Entrainment of sodium at the accelerated bubble liquid interfaces is mechanistically calculated by a Taylor instability entrainment model. Simulation of a hemispherical expansion form together with this mechanistic entrainment model gives a new integrated calculation of the time dependent sodium mass in the bubble. The paper summarizes the basic equations and assumptions of this computer model. Sample results compare different heat transfer and Na entrainment models during steel and fuel driven discharge processes. Mechanistic sodium entrainment simulation for SNR-type reactors coupled with a realistic heat transfer model is shown to reduce the integral mechanical work potential by a factor of 1.3 to 2.0 over the isentropic energy of the discharge working fluids. (orig.)

  13. DIF3D nodal neutronics option for two- and three-dimensional diffusion theory calculations in hexagonal geometry. [LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Lawrence, R.D.

    1983-03-01

    A nodal method is developed for the solution of the neutron-diffusion equation in two- and three-dimensional hexagonal geometries. The nodal scheme has been incorporated as an option in the finite-difference diffusion-theory code DIF3D, and is intended for use in the analysis of current LMFBR designs. The nodal equations are derived using higher-order polynomial approximations to the spatial dependence of the flux within the hexagonal-z node. The final equations, which are cast in the form of inhomogeneous response-matrix equations for each energy group, involved spatial moments of the node-interior flux distribution plus surface-averaged partial currents across the faces of the node. These equations are solved using a conventional fission-source iteration accelerated by coarse-mesh rebalance and asymptotic source extrapolation. This report describes the mathematical development and numerical solution of the nodal equations, as well as the use of the nodal option and details concerning its programming structure. This latter information is intended to supplement the information provided in the separate documentation of the DIF3D code.

  14. Comparison of numerical results with experimental data for single-phase natural convection in an experimental sodium loop. [LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Ribando, R.J.

    1979-01-01

    A comparison is made between computed results and experimental data for a single-phase natural convection test in an experimental sodium loop. The test was conducted in the Thermal-Hydraulic Out-of-Reactor Safety (THORS) facility, an engineering-scale high temperature sodium loop at the Oak Ridge National Laboratory (ORNL) used for thermal-hydraulic testing of simulated Liquid Metal Fast Breeder Reactor (LMFBR) subassemblies at normal and off-normal operating conditions. Heat generation in the 19 pin assembly during the test was typical of decay heat levels. The test chosen for analysis in this paper was one of seven natural convection runs conducted in the facility using a variety of initial conditions and testing parameters. Specifically, in this test the bypass line was open to simulate a parallel heated assembly and the test was begun with a pump coastdown from a small initial forced flow. The computer program used to analyze the test, LONAC (LOw flow and NAtural Convection) is an ORNL-developed, fast-running, one-dimensional, single-phase, finite-difference model used for simulating forced and free convection transients in the THORS loop.

  15. Weldability and joint properties of advanced carbon stabilized 2.25Cr-1Mo steel for LMFBR

    International Nuclear Information System (INIS)

    Terai, K.; Shimizu, S.; Nakai, Y.; Murakami, T.; Ota, S.; Fujiwara, M.

    1978-01-01

    A series of experimental tests have been carried out for weld cracking sensitivity and joint properties to establish the welding technique for 2.25Cr-1Mo-Nb and 2.25Cr-1Mo1Nb-Ni steels which have been newly developed as structural materials for LMFBR steam generators. The results are as follows:(i) The weld cracking sensitivity of 2.25Cr-1Mo-Nb steel is nearly equivalent to that of 2.25Cr-1Mo steel; (ii) The creep rupture strength and fatigue strength of 2.25Cr-1Mo-Nb steel and 2.25Cr-1Mo-Nb-Ni steel are equal to, or superior to that of 2.25Cr-1Mo steel. During tests, all materials rupture within base metal, and the tensile strengths are satisfactory. The impact value of 2.25Cr-1Mo-Nb steel is relatively low; on the other hand, the impact value of 2.25Cr-1Mo-Nb-Ni steel is satisfactory. (author)

  16. Pay for performance in the inpatient sector: A review of 34 P4P programs in 14 OECD countries.

    Science.gov (United States)

    Milstein, Ricarda; Schreyoegg, Jonas

    2016-10-01

    Across the member countries of the Organisation for Economic Co-operation and Development (OECD), pay-for-performance (P4P) programs have been implemented in the inpatient sector to improve the quality of care provided by hospitals. This paper provides an overview of 34 existing P4P programs in the inpatient sector in 14 OECD countries based on a structured literature search in five databases to identify relevant sources in Danish, English, French, German, Hebrew, Italian, Japanese, Korean, Norwegian, Spanish, Swedish and Turkish. It assembles information on the design and effects of these P4P systems and discusses whether evaluations of such programs allow preliminary conclusions to be drawn about the effects of P4P. The programs are very heterogeneous in their aim, the selection of indicators and the design of financial rewards. The impact of P4P is unclear and it may be that the moderately positive effects seen for some programs can be attributed to side effects, such as public reporting and increased awareness of data recording. Policy makers must decide whether the potential benefits of introducing a P4P program outweigh the potential risks within their particular national or regional context, and should be aware that P4P programs have yet not lived up to expectations. Copyright © 2016 Elsevier Ireland Ltd. All rights reserved.

  17. Biosynthesis and characterization of diblock copolymer of p(3-hydroxypropionate)-block-p(4-hydroxybutyrate) from recombinant Escherichia coli

    DEFF Research Database (Denmark)

    Tripathi, Lakshmi; Wu, Linping; Meng, Dechuan

    2013-01-01

    Poly(4-hydroxybutyrate) (P4HB) is a highly elastic polymer, whereas poly(3-hydroxypropionate) (P3HP) is a polymer with enormous tensile strength. This study aimed to biosynthesize a block copolymer consisting of soft P4HB block with a strong P3HP block to gain unique and excellent material...... properties. A recombinant Escherichia coli strain that produces homopolymers of P3HP and P4HB was employed for the block copolymer synthesis. When the strain was grown in the presence of 1,4-butanediol (BDO) as a 4HB precursor, P4HB block was formed. Sequential supplementation of 1,3-propanediol (PDO) as a 3......HP precursor allowed the strain to produce P3HP block. Thermal, NMR, fractionation, and mechanical characterizations confirmed the resulting polymer as a block copolymer of P3HP-b-P4HB. Two block copolymers were formed from this study, including the P3HP-b-29% P4HB and P3HP-b-37% P4HB, they showed...

  18. DNA Immunization with the Gene Encoding P4 Nuclease of Leishmania amazonensis Protects Mice against Cutaneous Leishmaniasis

    Science.gov (United States)

    Campbell, Kimberly; Diao, Hong; Ji, Jiaxiang; Soong, Lynn

    2003-01-01

    Infection with the protozoan parasite Leishmania amazonensis can cause diverse clinical forms of leishmaniasis. Immunization with purified P4 nuclease protein has been shown to elicit a protective response in mice challenged with L. amazonensis and L. pifanoi. To explore the potential of a DNA-based vaccine, we tested the L. amazonensis gene encoding P4 nuclease as well as adjuvant constructs encoding murine interleukin-12 (IL-12) and L. amazonensis HSP70. Susceptible BALB/c mice were immunized with the DNA encoding P4 alone, P4/IL-12, or P4/HSP70 prior to challenge with L. amazonensis promastigotes. Mice given P4/IL-12 exhibited no lesion development and had a 3- to 4-log reduction in tissue parasite burdens compared to controls. This protection corresponded to significant increases in gamma interferon and tumor necrosis factor alpha production and a reduction in parasite-specific immunoglobulin G1, suggesting an enhancement in Th1 responses. Moreover, we immunized mice with the L. amazonensis vaccines to determine if this vaccine regimen could provide cross-protection against a genetically diverse species, L. major. While the P4/HSP70 vaccine led to self-healing lesions, the P4/IL-12 vaccine provided negligible protection against L. major infection. This is the first report of successful use of a DNA vaccine to induce protection against L. amazonensis infection. Additionally, our results indicate that different vaccine combinations, including DNA encoding P4, HSP70, or IL-12, can provide significant protection against both Old World and New World cutaneous leishmaniasis. PMID:14573646

  19. Molecular Nickel Phosphide Carbonyl Nanoclusters: Synthesis, Structure, and Electrochemistry of [Ni11P(CO)18]3- and [H6-nNi31P4(CO)39]n- (n = 4 and 5).

    Science.gov (United States)

    Capacci, Chiara; Ciabatti, Iacopo; Femoni, Cristina; Iapalucci, Maria Carmela; Funaioli, Tiziana; Zacchini, Stefano; Zanotti, Valerio

    2018-02-05

    The reaction of [NEt 4 ] 2 [Ni 6 (CO) 12 ] in thf with 0.5 equiv of PCl 3 affords the monophosphide [Ni 11 P(CO) 18 ] 3- that in turn further reacts with PCl 3 resulting in the tetra-phosphide carbonyl cluster [HNi 31 P 4 (CO) 39 ] 5- . Alternatively, the latter can be obtained from the reaction of [NEt 4 ] 2 [Ni 6 (CO) 12 ] in thf with 0.8-0.9 equiv of PCl 3 . The [HNi 31 P 4 (CO) 39 ] 5- penta-anion is reversibly protonated by strong acids leading to the [H 2 Ni 31 P 4 (CO) 39 ] 4- tetra-anion, whereas deprotonation affords the [Ni 31 P 4 (CO) 39 ] 6- hexa-anion. The latter is reduced with Na/naphthalene yielding the [Ni 31 P 4 (CO) 39 ] 7- hepta-anion. In order to shed light on the polyhydride nature and redox behavior of these clusters, electrochemical and spectroelectrochemical studies were carried out on [Ni 11 P(CO) 18 ] 3- , [HNi 31 P 4 (CO) 39 ] 5- , and [H 2 Ni 31 P 4 (CO) 39 ] 4- . The reversible formation of the stable [Ni 11 P(CO) 18 ] 4- tetra-anion is demonstrated through the spectroelectrochemical investigation of [Ni 11 P(CO) 18 ] 3- . The redox changes of [HNi 31 P 4 (CO) 39 ] 5- show features of chemical reversibility and the vibrational spectra in the ν CO region of the nine redox states of the cluster [HNi 31 P 4 (CO) 39 ] n- (n = 3-11) are reported. The spectroelectrochemical investigation of [H 2 Ni 31 P 4 (CO) 39 ] 4- revealed the presence of three chemically reversible reduction processes, and the IR spectra of [H 2 Ni 31 P 4 (CO) 39 ] n- (n = 4-7) have been recorded. The different spectroelectrochemical behavior of [HNi 31 P 4 (CO) 39 ] 5- and [H 2 Ni 31 P 4 (CO) 39 ] 4- support their formulations as polyhydrides. Unfortunately, all the attempts to directly confirm their poly hydrido nature by 1 H NMR spectroscopy failed, as previously found for related large metal carbonyl clusters. Thus, the presence and number of hydride ligands have been based on the observed protonation/deprotonation reactions and the spectroelectrochemical

  20. Surveillance of a nuclear reactor by pattern recognition analysis of the neutronic noise. Experience on Phenix LMFBR

    International Nuclear Information System (INIS)

    Le Guillou, G.; Bernardin, B.

    1980-05-01

    The purpose of this paper is to present some results of pattern recognition methods applied to the problem of supervising the behaviour of a nuclear reactor, especially the sodium cooled fast breeder Phenix. The problem to solve can be divided into two parts: first, from a set of data about the behaviour of the reactor, we have to find consistent classes of functionning. These classes must be interpreted by physical considerations; then, we have to elaborate a simple classification algorithm, which can be used in-line, to improve safety systems of fast breeder reactors, by giving helpful information for decision making. The neutronic noise has been chosen for our study

  1. Application of 2-1/4 Cr-1 Mo as a structural material in saturated steam cycle LMFBR systems. Final report

    International Nuclear Information System (INIS)

    Licina, G.J.; Busboom, H.J.; Ring, P.J.; Roy, P.; Schmidt, C.G.; Spalaris, C.N.

    1982-02-01

    The suitability and incentives were examined for using 2-1/4Cr-1Mo steel as a structural material for the entire primary and secondary sodium systems in a 1000 MWe pool-type Liquid Metal Fast Breeder Reactor. The critical properties, advantages and disadvantages of 2-1/4Cr-1Mo, and data needed for design were described for each major component in the reactor. The relative importance of alloy properties to the successful use of ferritics in LMFBR was identified. Licensing issues, likely to surface if ferritic alloys were to be used for critical reactor components, were discussed

  2. Sodium-water wastage and reactions program performed by general electric in support of the US. AEC LMFBR steam generator development

    International Nuclear Information System (INIS)

    Greene, D.A.

    1975-01-01

    This paper constitutes an interim report on the sodium-water reaction programs performed, using the GE-SOWAT, GE-SMALL LEAK BEHAVIOR RIG, and GE-PTTR facilities in support of LMFBR steam generator development and its application to the Clinch River Breeder Reactor Plant. Test data from these rigs are presented, including wastage data as a function of water injection rate, sodium temperature, and orifice geometry. Initial results for self-wastage of defects under prototypical conditions, and from proof-of-principle tests of a protected heat transfer tube concept are also presented. An analytical basis for wastage phenomena is suggested. (author)

  3. Comparative analysis of a hypothetical loss-of-flow accident in an irradiated LMFBR core using different computer models for a common benchmark problem

    International Nuclear Information System (INIS)

    Wider, H.U.; Devos, J.; Nguyen, H.; Goethem, G. Van.; Miles, K.J.; Tentner, A.M.; Pizzica, P.

    1989-01-01

    This report summarizes the results of an international exercise to compare whole-core accident calculations of the initiation phase of an unprotected LOF accident in a large irradiated LMFBR. The results for the accident phase before pin failure are in rather good agreement except for the fuel pin mechanics predictions. There are also some differences in the sodium boiling calculations but the voiding rates which are of key importance are very similar. The post - failure fuel motion and sodium voiding predictions show significant differences. However, the majority of these calculations agree that temporary fuel accumulations occur which increase the power beyond that caused by sodium voiding alone

  4. On the hazard accumulation of actinide waste in a Pu-fueled LMFBR power economy with and without by-product actinide recycling

    International Nuclear Information System (INIS)

    Anselmi, L.; Caruso, K.; Hage, W.; Schmidt, E.

    1979-01-01

    The actinide waste arisings in terms of hazard potential for ingestion and inhalation are given for a Pu-fueled LMFBR Power Economy as function of decay time. The data were assessed for two simplified fuel cycles, one considering the recycling of by-product actinides and the other their complete discharge to the high-level waste. Two durations of nuclear power and several loss fractions of actinides to the waste were considered. The major contributors in form of chemical elements or isotopes to the actinide waste hazard built up during the nuclear power duration were identified for various decay intervals

  5. Effects of duct configuration on flow and temperature structure in sodium-cooled 19-rod simulated LMFBR fuel bundles with helical wire-wrap spacers

    International Nuclear Information System (INIS)

    Wantland, J.L.; Fontana, M.H.; Gnadt, P.A.; Hanus, N.; MacPherson, R.E.; Smith, C.M.

    1976-01-01

    Thermal-hydrodynamic testing of sodium-cooled 19-rod simulated LMFBR fuel bundles is being conducted at the O ak Ridge National Laboratory in the Fuel Failure Mockup (FFM), an engineering-scale high-temperature sodium facility which provides prototypic flows, temperatures and power densities. Electrically heated bundles have been tested with two scalloped and two hexagonal duct configurations. Peripheral helical flows, attributed to the spacers, have been observed with strengths dependent upon the evenness and relative sizes of the peripheral flow areas. Diametral sodium temperature profiles are more uniform with smaller peripheral flow areas

  6. A study on integrity of LMFBR secondary cooling system to hypothetical tube failure propagation in the steam generator

    International Nuclear Information System (INIS)

    Yoshihisa Shindo; Kazuo Haga

    2005-01-01

    Full text of publication follows: A fundamental safety issue of liquid-metal-cooled fast breeder reactor (LMFBR) is to maintain the integrity of the secondary cooling system components against violent chemical sodium-water reaction caused by the water leak from the heat transfer tube of steam generators (SG). The produced sodium-water reaction jet would attack more severely surrounding tubes and would cause other tube failures (tube failure propagation), if it was assumed that the water leak was not detected by function-less detectors and proper operating actions to mitigate the tube failure propagation, such as isolations of the SG from the secondary cooling system and turbine water/steam system, and blowing water and steam inside tubes in the SG, were not taken. This study has been made focusing on the affection of large-scale water leak enlarged due to SG tube failure propagation to the structural integrity of the secondary cooling system because the generated pressure pulse caused by a large-scale sodium-water reaction might break heat transfer tubes of the intermediate heat exchanger (IHX). The present work has been made as one part of the study of probabilistic safety assessment (PSA) of LMFBR, because if the heat-transfer tubes of IHX were failed, the reactor core may be affected by the pressure pulse and/or by the sodium-water reaction products transported through the primary cooling system. As tools for PSA of the water leak incident of SG, we have developed QUARK-LP Version 4 code that mainly analyzes the high temperature rupture phenomena and estimates the number of failed tubes during the middle-scale water leak. The pressure pulse behavior generated by sodium-water reaction in the failure SG and the pressure propagation in the secondary cooling system are calculated by using the SWAAM-2 code developed by ANL. Furthermore, the quasi-steady state high pressure and temperature of the secondary cooling system in a long term is estimated by using the SWAAM

  7. Complex reassortment events of unusual G9P[4] rotavirus strains in India between 2011 and 2013.

    Science.gov (United States)

    Doan, Yen Hai; Suzuki, Yoshiyuki; Fujii, Yoshiki; Haga, Kei; Fujimoto, Akira; Takai-Todaka, Reiko; Someya, Yuichi; Nayak, Mukti K; Mukherjee, Anupam; Imamura, Daisuke; Shinoda, Sumio; Chawla-Sarkar, Mamta; Katayama, Kazuhiko

    2017-10-01

    Rotavirus A (RVA) is the predominant etiological agent of acute gastroenteritis in young children worldwide. Recently, unusual G9P[4] rotavirus strains emerged with high prevalence in many countries. Such intergenogroup reassortant strains highlight the ongoing spread of unusual rotavirus strains throughout Asia. This study was undertaken to determine the whole genome of eleven unusual G9P[4] strains detected in India during 2011-2013, and to compare them with other human and animal global RVAs to understand the exact origin of unusual G9P[4] circulating in India and other countries worldwide. Of these 11 RVAs, four G9P[4] strains were double-reassortants with the G9-VP7 and E6-NSP4 genes on a DS-1-like genetic backbone (G9-P[4]-I2-R2-C2-M2-A2-N2-T2-E6-H2). The other strains showed a complex genetic constellation, likely derived from triple reassortment event with the G9-VP7, N1-NSP2 and E6-NSP4 on a DS-1-like genetic backbone (G9-P[4]-I2-R2-C2-M2-A2-N1-T2-E6-H2). Presumably, these unusual G9P[4] strains were generated after several reassortment events between the contemporary co-circulating human rotavirus strains. Moreover, the point mutation S291L at the interaction site between inner and outer capsid proteins of VP6 gene may be important in the rapid spread of this unusual strain. The complex reassortment events within the G9[4] strains may be related to the high prevalence of mixed infections in India as reported in this study and other previous studies. Copyright © 2017. Published by Elsevier B.V.

  8. Serum levels of acute phase proteins: SAA, Hp and progesterone (P4) in mares with early embryonic death.

    Science.gov (United States)

    Krakowski, L; Krawczyk, C H; Kostro, K; Stefaniak, T; Novotny, F; Obara, J

    2011-08-01

    The study involved 46 healthy purebred Arabian mares exhibiting regular oestrous cycles that underwent artificial insemination (AI). Pregnancy was detected ultrasonographically (US) in 40 mares. In 15 mares in foal, early embryonic death (EED) was observed during the pregnancy days 14-21. Blood for determinations of serum acute phase proteins (SAA and Hp) and progesterone (P4) was sampled 12-24 h before ovulation and the first insemination, at 12, 24, 72, 96 h and on day 7, 10, 14, 21, 35 and 55 after ovulation. The results revealed that in 25 mares without EED, the serum levels of P4, SAA and Hp were within physiological limits; in 15 mares with EED, the levels of SAA and Hp were significantly increased. In seven mares with EED, high levels of SAA and Hp were already found before ovulation and at 12, 24, 72, 96 h as well as on day 7 and 10 post-ovulation, whereas the level of P4 was normal for early pregnancy. In the remaining eight mares with EED, increased levels of SAA and Hp were found at 72 h after ovulation and maintained until day 55. In this group, the level of P4 decreased since 96 h after ovulation. Determinations of SAA, Hp and P4 in mares in early pregnancy (EP) are useful for monitoring normal development of pregnancy and for diagnosis of subclinical genital inflammations, which may lead to EED. © 2011 Blackwell Verlag GmbH.

  9. Reinterpretation of the recently measured absolute generalized oscillator strength for the Ar 3p-4p transition

    International Nuclear Information System (INIS)

    Msezane, A.Z.; Felfli, Z.; Chen, Z.; Amusia, M.Ya.; Chernysheva, L. V.

    2002-01-01

    The recent experimental observation of the absolute generalized oscillator strength (GOS) for the Ar 3p-(4p,4p ' ) nondipole transition has been interpreted as a manifestation of quadrupole excitation [X. W. Fan and K. T. Leung, Phys. Rev. A 62, 062703 (2000)]. Contrary to the experimentalists' assignment, on the grounds of our random-phase-approximation with exchange (RPAE) calculation, we attribute the measured GOS to combined monopole, the dominant component, and quadrupole contributions. Our RPAE GOS's for the Ar dipole 3p-4s and 3p-3d,5s and the lowest nondipole transitions are compared with the measurements. The results could have significant implications for other similar transitions, previously interpreted as quadrupole excitation and for interpreting other discrete transitions

  10. Proceedings of the specialists' meeting on steam generator failure and failure propagation experience, held in Aix-en Provence, France, 26-28 September 1990

    International Nuclear Information System (INIS)

    Maupre, J.P.

    1990-09-01

    The 35 participants, representing 7 Member States and one International Organization discussed recent investigations on leak development and propagation in LMFBR steam generators. The meeting was divided into three technical sessions: review of national status on studies of failure propagation (8 papers); propagation experience on reactor steam generators (4 papers); studies of failure propagation: codes, hydrogen detection, tests (11 papers). A separate abstract was prepared for each of these papers

  11. Luteal P4 synthesis in early pregnant gilts after induction of estrus with PMSG/hCG.

    Science.gov (United States)

    Blitek, Agnieszka; Szymanska, Magdalena; Pieczywek, Marta; Morawska-Pucinska, Ewa

    2016-03-01

    The present study was designed to examine whether an estrus induction with gonadotropins could affect luteal P4 synthesis in early pregnant gilts. Sixteen prepubertal gilts received 750IU of PMSG and 500IU of hCG 72h later. Prepubertal gilts in the control group (n=17) were observed daily for estrus behavior. All gilts were inseminated in their first estrus. Corpora lutea (CLs) were collected on days 10, 12 and 15 of pregnancy and analyzed for (1) the mRNA and protein expression of steroidogenic acute regulatory protein (StAR), cytochrome P450 family 11 subfamily A polypeptide 1 (CYP11A1), and 3β-hydroxysteroid dehydrogenase (3βHSD); (2) the tissue concentration of P4; and (3) the mRNA expression of luteinizing hormone receptor (LHR) and estrogen receptors (ESR1 and ESR2). Additionally, P4 concentration was analyzed in blood serum of all animals. PMSG/hCG injections to induce estrus decreased mRNA expression of StAR, CYP11A1 and 3βHSD on day 10 and CYP11A1 on day 12 of pregnancy compared with the control group, while CYP11A1 and 3βHSD proteins were down-regulated on day 10 in the hormonally-treated gilts. Concentrations of P4 in luteal tissue and blood serum were also lower in animals after gonadotropin-induced estrus. In contrast, LHR and ESR1 mRNA expression was greater in PMSG/hCG-treated than control gilts on day 15 of gestation. In conclusion, induction of estrus with a PMSG/hCG protocol in prepubertal gilts impaired expression of the luteal P4 synthesis system. Low P4 content may, in turn, induce local mechanisms involving LHR and ESR1 expression to support CL function. Copyright © 2016 Elsevier B.V. All rights reserved.

  12. Synthesis of clad motion experiments interpretation: codes and validation

    International Nuclear Information System (INIS)

    Papin, J.; Fortunato, M.; Seiler, J.M.

    1983-04-01

    This communication deals with clad melting and relocation phenomena related to LMFBR safety analysis of loss of flow accidents. We present: - the physical models developed at DSN/CEN Cadarache in single channel and bundle geometry. The interpretation with these models of experiments performed by the STT (CEN Grenoble). It comes out that we have now obtained a good understanding of the involved phenomena in single channel geometry. On the other hand, further studies are necessary for a better knowledge of clad motion phenomena in bundle cases with conditions close to reactor ones

  13. Bioinformatics Analysis and Characterization of Highly Efficient Polyvinyl Alcohol (PVA)-Degrading Enzymes from the Novel PVA Degrader Stenotrophomonas rhizophila QL-P4.

    Science.gov (United States)

    Wei, Yahong; Fu, Jing; Wu, Jianying; Jia, Xinmiao; Zhou, Yunheng; Li, Cuidan; Dong, Mengxing; Wang, Shanshan; Zhang, Ju; Chen, Fei

    2018-01-01

    Polyvinyl alcohol (PVA) is used widely in industry, and associated environmental pollution is a serious problem. Herein, we report a novel, efficient PVA degrader, Stenotrophomonas rhizophila QL-P4, isolated from fallen leaves from a virgin forest in the Qinling Mountains. The complete genome was obtained using single-molecule real-time (SMRT) technology and corrected using Illumina sequencing. Bioinformatics analysis revealed eight PVA/vinyl alcohol oligomer (OVA)-degrading genes. Of these, seven genes were predicted to be involved in the classic intracellular PVA/OVA degradation pathway, and one (BAY15_3292) was identified as a novel PVA oxidase. Five PVA/OVA-degrading enzymes were purified and characterized. One of these, BAY15_1712, a PVA dehydrogenase (PVADH), displayed high catalytic efficiency toward PVA and OVA substrate. All reported PVADHs only have PVA-degrading ability. Most importantly, we discovered a novel PVA oxidase (BAY15_3292) that exhibited higher PVA-degrading efficiency than the reported PVADHs. Further investigation indicated that BAY15_3292 plays a crucial role in PVA degradation in S. rhizophila QL-P4. Knocking out BAY15_3292 resulted in a significant decline in PVA-degrading activity in S. rhizophila QL-P4. Interestingly, we found that BAY15_3292 possesses exocrine activity, which distinguishes it from classic PVADHs. Transparent circle experiments further proved that BAY15_3292 greatly affects extracellular PVA degradation in S. rhizophila QL-P4. The exocrine characteristics of BAY15_3292 facilitate its potential application to PVA bioremediation. In addition, we report three new efficient secondary alcohol dehydrogenases (SADHs) with OVA-degrading ability in S. rhizophila QL-P4; in contrast, only one OVA-degrading SADH was reported previously. IMPORTANCE With the widespread application of PVA in industry, PVA-related environmental pollution is an increasingly serious issue. Because PVA is difficult to degrade, it accumulates in aquatic

  14. Mechanism and significance of P4 ATPase-catalyzed lipid transport: lessons from a Na+/K+-pump

    NARCIS (Netherlands)

    Puts, C.F.; Holthuis, J.C.M.

    2009-01-01

    Members of the P4 subfamily of P-type ATPases are believed to catalyze phospholipid transport across membrane bilayers, a process influencing a host of cellular functions. Atomic structures and functional analysis of P-type ATPases that pump small cations and metal ions revealed a transport

  15. Fine structure and ionization energy of the 1s2s2p 4P state of the helium negative ion He-.

    Science.gov (United States)

    Wang, Liming; Li, Chun; Yan, Zong-Chao; Drake, G W F

    2014-12-31

    The fine structure and ionization energy of the 1s2s2p (4)P state of the helium negative ion He(-) are calculated in Hylleraas coordinates, including relativistic and QED corrections up to O(α(4)mc(2)), O((μ/M)α(4)mc(2)), O(α(5)mc(2)), and O((μ/M)α(5)mc(2)). Higher order corrections are estimated for the ionization energy. A comparison is made with other calculations and experiments. We find that the present results for the fine structure splittings agree with experiment very well. However, the calculated ionization energy deviates from the experimental result by about 1 standard deviation. The estimated theoretical uncertainty in the ionization energy is much less than the experimental accuracy.

  16. Experimental study of large scale axially heterogeneous LMFBR core at FCA, (3)

    International Nuclear Information System (INIS)

    Iijima, Susumu; Okajima, Sigeaki; Sanda, Toshio

    1985-04-01

    FCA Assembly XII-1 is the second core in axial heterogeneous core experiment program at FCA and is a standard experimental core for the measurements of the axial nuclear characteristics in the axial heterogeneous core. Following nuclear characteristics have been measured, (i) criticality, (ii) sodium void and sample reactivity worths, (iii) reaction rates and ratios, (iv) Doppler reactivity worth, (v) B 4 C control rod worth and (vi) gamma heating. Following the standard core experiment, sample worths and reaction rate distributions has been measured using the assembly with B 4 C control rod at a central region. In order to examin data and method for the calculation of nuclear characteristics of the axial heterogeneous core, experimental analysis has been performed using nuclear data library JENDL-2 and JAERI's nuclear characteristics calculation system for a fast reactor. (author)

  17. Effect of Synthetic Levers on Nickel Phosphide Nanoparticle Formation: Ni5P4 and NiP2.

    Science.gov (United States)

    Li, Da; Senevirathne, Keerthi; Aquilina, Lance; Brock, Stephanie L

    2015-08-17

    Due to their unique catalytic, electronic, and redox processes, Ni5P4 and NiP2 nanoparticles are of interest for a wide-range of applications from the hydrogen evolution reaction to energy storage (batteries); yet synthetic approaches to these materials are limited. In the present work, a phase-control strategy enabling the arrested-precipitation synthesis of nanoparticles of Ni5P4 and NiP2 as phase-pure samples using different Ni organometallic precursors and trioctylphosphine (TOP) is described. The composition and purity of the product can be tuned by changing key synthetic levers, including the Ni precursor, the oleylamine (OAm) coordinating solvent and TOP concentrations, temperature, time, and the presence or absence of a moderate temperature soak step to facilitate formation of Ni and/or Ni-P amorphous nanoparticle intermediates. Notably, the 230 °C intermediate step favors the ultimate formation of Ni2P and hinders further phosphidation to form Ni5P4 or NiP2 as phase-pure products. In the absence of this step, increasing the P/Ni ratio (13-20), reaction temperature (350-385 °C), and time (10-48 h) favors more P-rich phases, and these parameters can be adjusted to generate either Ni5P4 or NiP2. The phase of the obtained particles can also be tuned between pure Ni2P to Ni5P4 and NiP2 by simply decreasing the OAm/TOP ratio and/or changing the nickel precursor (nickel(II)acetylacetonate, nickel(II)acetate tetrahydrate, or bis(cyclooctadiene)nickel(0)). However, at high concentrations of OAm, the product formed is the same regardless of Ni precursor, suggesting the formation of a uniform Ni intermediate (an Ni-oleylamine complex) under these conditions that is responsible for product distribution. Intriguingly, under the extreme phosphidation conditions required to favor Ni5P4 and NiP2 over Ni2P (large excess of TOP), the 20-30 nm crystallites assemble into supraparticles with diameters of 100-500 nm. These factors are discussed in light of a comprehensive

  18. LMFBR. Off normal, transient test facilities and programs in the USA

    International Nuclear Information System (INIS)

    Herbst, R.J.

    1985-01-01

    The United States fast breeder reactor development program has included operational transient analyses and experiments to verify the predicted performance of core components. Operational transient testing has focused on off-normal operation during Plant Protection System terminated transient-overpower events. In-pile and out-of-pile tests have been used to simulate predicted thermal and mechanical strain cycles and measure component response. The spectrum of reactivity ramp rates investigated in TOP tests has recently been expanded to include rates of less than $0.1/s. These slow ramp rate studies are being done in cooperation with the Japanese. The US has also cooperated with the UK in the transient testing of Prototype Fast Reactor fuel pins

  19. Detection of coolant disturbances in the fuel elements of an LMFBR by temperature fluctuation analysis

    International Nuclear Information System (INIS)

    Weinkoetz, G.; Martin, H.; Krebs, L.

    1980-01-01

    Sodium temperature noise measurements were performed at the coolant fluid outlets of an electrically heated 169-rod bundle and also a 28-rod bundle, with different partially blocked coolant sections. On both test assemblies, a flow mixer was installed downstream of the bundle fluid exit plane. For all tests, measuring planes with three-wire thermocouples containing both steel-sodium and chromel-alumel junctions were located on the upstream and downstream sides of the flow mixer. Statistical parameters such as the root mean square (RMS) and the power spectral density (PSD) of temperature fluctuations were investigated. The influences of flow velocity, heat flux, thermocouple cut-off frequency, and different blockage sizes on these statistical parameters were analysed. Moreover, an essential result of interpretation of the experiments is that a characteristic geometrical bundle coefficient was found which indicates coolant channel disturbances only, independent of the operational conditions of the bundles such as heat flux and flow velocity. (orig.)

  20. Proceedings of a seminar on the potential for LMFBR boiling detection by acoustic/neutronic monitoring, Argonne, Illinois, April 8--9, 1976

    Energy Technology Data Exchange (ETDEWEB)

    Carey, W.M.; Albrecht, R.W.

    1976-06-01

    A seminar involving ten technical presentations by principal investigators was held to assess the current scope of ERDA-sponsored programs to determine the feasibility of sodium-boiling detection in LMFBRs and to establish areas in need of additional research and development. The consensus was that (1) feasibility of boiling detection by acoustic, neutronic, and acoustic/neutronic monitors has been demonstrated in U.S. and European programs; (2) additional research and development is needed in areas of reactor noise, cavitation, and the effects of noncondensible gases on sound source levels and transmission; (3) the role of acoustic/neutronic monitors from the standpoint of reactor surveillance rather than reactor safety is a viable approach to be adapted; and, in particular (4) a need exists for an operational LMFBR demonstration system. Each paper has been separately abstracted and indexed. (DG)

  1. First principles electronic structure and optical properties of the Zintl compound Eu3In2P4

    KAUST Repository

    Singh, Nirpendra

    2011-05-01

    We have performed full-potential calculations of the electronic structure and optical properties of the newly found Zintl compound Eu3In 2P4. Eu3In2P4 turns out to be a small gap semiconductor with an energy gap of 0.42 eV, which is in agreement with the experimental value of 0.452 eV. The peaks of the optical spectra originate mainly from transitions between occupied Eu 4f states in the valence band and unoccupied Eu 5d states in the conduction band. A considerable anisotropy is observed for the parallel and perpendicular components in the frequency dependent optical spectra. The spectral features are explained in terms of the band structure. © 2011 Elsevier B.V. All rights reserved.

  2. Clinical Applications of S53P4 Bioactive Glass in Bone Healing and Osteomyelitic Treatment: A Literature Review

    Directory of Open Access Journals (Sweden)

    N. A. P. van Gestel

    2015-01-01

    Full Text Available Nowadays, S53P4 bioactive glass is indicated as a bone graft substitute in various clinical applications. This review provides an overview of the current published clinical results on indications such as craniofacial procedures, grafting of benign bone tumour defects, instrumental spondylodesis, and the treatment of osteomyelitis. Given the reported results that are based on examinations, such as clinical examinations by the surgeons, radiographs, CT, and MRI images, S53P4 bioactive glass may be beneficial in the various reported applications. Especially in craniofacial reconstructions like mastoid obliteration and orbital floor reconstructions, in grafting bone tumour defects, and in the treatment of osteomyelitis very promising results are obtained. Randomized clinical trials need to be performed in order to determine whether bioactive glass would be able to replace the current golden standard of autologous bone usage or with the use of antibiotic containing PMMA beads (in the case of osteomyelitis.

  3. Crystal structure of (Al,V)4(P4O12)3, archetype of double cubic ring tetraphosphate

    International Nuclear Information System (INIS)

    Yakubovich, O. V.; Biralo, G. V.; Dimitrova, O. V.

    2012-01-01

    The crystal structure of the (Al,V) 4 (P 4 O 12 ) 3 solid solution, obtained in the single-crystal form by hydrothermal synthesis in the Al(OH) 3 -VO 2 -NaCl-H 3 PO 4 -H 2 O system, has been solved by X-ray diffraction analysis (Xcalibur-S-CCD diffractometer, R = 0.0257): a = 13.7477(2) Å, sp. gr. I 4 bar 3d, Z = 4, and ρ calcd = 2.736 g/cm 3 . It is shown that the crystal structure of the parent cubic Al 4 (P 4 O 12 ) 3 modification can formally be considered an archetype for the formation of double isosymmetric tetraphosphates on its basis.

  4. Extending The P4P Agenda, Part 1: How Medicare Can Improve Patient Decision Making And Reduce Unnecessary Care

    Science.gov (United States)

    Wennberg, John E.; O'Connor, Annette M.; Collins, E. Dale; Weinstein, James N.

    2008-01-01

    The decision to undergo many discretionary medical treatments should be based on informed patient choice. Shared decision making is an effective strategy for achieving this goal. The Centers for Medicare and Medicaid Services (CMS) should extend its pay-for-performance (P4P) agenda to assure that all Americans have access to a certified shared decision-making process. This paper outlines a strategy to achieve informed patient choice as the standard of practice for preference-sensitive care. PMID:17978377

  5. New high-pressure polymorph of In2S3 with defect Th3P4-type structure

    Science.gov (United States)

    Lai, Xiaojing; Zhu, Feng; Wu, Ye; Huang, Rong; Wu, Xiang; Zhang, Qian; Yang, Ke; Qin, Shan

    2014-02-01

    The high pressure behavior of β-In2S3 (I41/amd and Z=16) has been studied by in situ synchrotron radiation X-ray diffraction combined with diamond anvil cell up to 71.7 GPa. Three pressure-induced phase transitions are evidenced at ~6.6 GPa, ~11.1 GPa at room temperature and 35.6 GPa after the high-temperature annealing using a portable laser heating system. The new polymorph of In2S3 at 35.6 GPa is assigned to the denser cubic defect Th3P4 structure (I4bar3d and Z=5.333), whose unit-cell parameters are a=7.557(1) Å and V=431.6(2) Å3. The Th3P4-type phase can be stable at least up to 71.7 GPa and cannot be preserved at ambient pressure. The pressure-volume relationship is well described by the second-order Birch-Murnaghan Equation of State, which yields B0=63(3) GPa and B0‧=4 (fixed) for the β-In2S3 phase and B0=87(3) GPa and B0‧=4 (fixed) for the defect Th3P4-type phase respectively.

  6. Subtelomeric Copy Number Variations: The Importance of 4p/4q Deletions in Patients with Congenital Anomalies and Developmental Disability.

    Science.gov (United States)

    Novo-Filho, Gil M; Montenegro, Marília M; Zanardo, Évelin A; Dutra, Roberta L; Dias, Alexandre T; Piazzon, Flavia B; Costa, Taís V M M; Nascimento, Amom M; Honjo, Rachel S; Kim, Chong A; Kulikowski, Leslie D

    2016-01-01

    The most prevalent structural variations in the human genome are copy number variations (CNVs), which appear predominantly in the subtelomeric regions. Variable sizes of 4p/4q CNVs have been associated with several different psychiatric findings and developmental disability (DD). We analyzed 105 patients with congenital anomalies (CA) and developmental and/or intellectual disabilities (DD/ID) using MLPA subtelomeric specific kits (P036 /P070) and 4 of them using microarrays. We found abnormal subtelomeric CNVs in 15 patients (14.3%), including 8 patients with subtelomeric deletions at 4p/4q (53.3%). Additional genomic changes were observed at 1p36, 2q37.3, 5p15.3, 5q35.3, 8p23.3, 13q11, 14q32.3, 15q11.2, and Xq28/Yq12. This indicates the prevalence of independent deletions at 4p/4q, involving PIGG, TRIML2, and FRG1. Furthermore, we identified 15 genes with changes in copy number that contribute to neurological development and/or function, among them CRMP1, SORCS2, SLC25A4, and HELT. Our results highlight the association of genes with changes in copy number at 4p and 4q subtelomeric regions and the DD phenotype. Cytogenomic characterization of additional cases with distal deletions should help clarifying the role of subtelomeric CNVs in neurological diseases. © 2016 S. Karger AG, Basel.

  7. Benchmark calculations on fluid coupled co-axial cylinders typical to LMFBR structures

    International Nuclear Information System (INIS)

    Dostal, M.; Descleve, P.; Gantenbein, F.; Lazzeri, L.

    1983-01-01

    This paper describes a joint effort promoted and funded by the Commission of European Community under the umbrella of Fast Reactor Co-ordinating Committee and working group on Codes and Standards No. 2 with the purpose to test several programs currently used for dynamic analysis of fluid-coupled structures. The scope of the benchmark calculations is limited to beam type modes of vibration, small displacement of the structures and small pressure variation such as encountered in seismic or flow induced vibration problems. Five computer codes were used: ANSYS, AQUAMODE, NOVAX, MIAS/SAP4 and ZERO where each program employs a different structural-fluid formulation. The calculations were performed for four different geometrical configurations of concentric cylinders where the effect of gap size, water level, and support conditions were considered. The analytical work was accompanied by experiments carried out on a purpose-built rig. The test rig consisted of two concentric cylinders independently supported on flexible cantilevers. A geometrical simplicity and attention in the rig design to eliminate the structural coupling between the cylinders lead to unambiguous test results. Only the beam natural frequencies, in phase and out of phase were measured. The comparison of different analytical methods and experimental results is presented and discussed. The degree of agreement varied between very good and unacceptable. (orig./GL)

  8. Stainless steel corrosion in French LMFBR - Feedback and prevention against risks

    International Nuclear Information System (INIS)

    Grabon, V.; Brissonneau, L.; Billey, C.

    2015-01-01

    This paper deals with the mechanisms and the conditions leading to the most threatening corrosion risks specific to the use of sodium at high temperature as coolant in FBR (Fast Breeder Reactors) - apart from wastage (rapid erosion-corrosion of the steam generator tubes by sodium hydroxide due to steam-water leaks in sodium): Stress Corrosion Cracking (SCC) induced in sodium polluted by sodium hydroxide (following sodium-water reaction or incomplete cleaning of component), SCC induced by caustic solution during maintenance operations (cleaning of component or repair on drained sodium circuit inducing moist air ingress), and Intergranular Attack (IGA) induced on sensitized stainless steels by acid solutions used during maintenance operations (decontamination of component, chemical cleaning). These risks are illustrated by some examples of corrosion encountered through Phenix experience or in CEA sodium loops. The paper also describes the solutions and the preventive measures that have been put in place against these corrosion risks, in the form of design rules and operating procedures. Generally the plant operator cannot control the material parameters (metal composition, aging, stress) during the lifetime of the facility. Thus most of the time preventive measures consist in excluding at least one of the two other factors related to the chemical environment and/or to the operating conditions. Moreover corrosion of the primary components during cleaning and decontamination operations before repairing should be carefully examined to authorize their reuse in the reactor

  9. Interim report on the feasibility study of acoustic leak location for WTD steam generators. [LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Greene, D.A.; McMurtrie, K.A.

    1979-03-01

    This interim report summarizes the current status of a feasibility study of an acoustic leak location system for two Westinghouse-Tampa Division (WTD) double-wall steam generators. The primary WTD design requirement is that a leak of helium gas into sodium be located to within a cluster of seven tubes at hot standby conditions. The report documents the results of an extensive analytical assessment, outlines areas of concern resulting from the analyses which will require experimental validation, and presents results of experiments thus far completed. The conclusion of the study at this time is that acoustic leak location is feasible, pending the results of the remaining experimental tests. The acoustic leak location system operates on the same principles as the acoustic leak detection system being developed under SG027, Subtask X2. Analyses indicate that, in general, the location system will use similar design parameters to the acoustic leak detection system. Much of the hardware can be indentical, in particular the accelerometers. It is recommended that a minicomputer/software approach be employed rather than the custom-designed hardware approach used for the detection system.

  10. A Switchable Molecular Dielectric with Two Sequential Reversible Phase Transitions: [(CH3)4P]4[Mn(SCN)6].

    Science.gov (United States)

    Li, Qiang; Shi, Ping-Ping; Ye, Qiong; Wang, Hui-Ting; Wu, De-Hong; Ye, Heng-Yun; Fu, Da-Wei; Zhang, Yi

    2015-11-16

    A new organic-inorganic hybrid switchable and tunable dielectric compound, [(CH3)4P]4[Mn(SCN)6] (1), exhibits three distinct dielectric states above room temperature and undergoes two reversible solid-state phase transitions, including a structural phase transition at 330 K and a ferroelastic phase transition with the Aizu notation of mmmF2/m at 352 K. The variable-temperature structural analyses disclose that the origin of the phase transitions and dielectric anomalies can be ascribed to the reorientation or motion of both the [(CH3)4P](+) cations and [Mn(SCN)6](4-) anions in solid-state crystals.

  11. Influence of SrO substitution for CaO on the properties of bioactive glass S53P4.

    Science.gov (United States)

    Massera, Jonathan; Hupa, Leena

    2014-03-01

    Commercial melt-quenched bioactive glasses consist of the oxides of silicon, phosphorus, calcium and sodium. Doping of the glasses with oxides of some other elements is known to affect their capability to support hydroxyapatite formation and thus bone tissue healing but also to modify their high temperature processing parameters. In the present study, the influence of gradual substitution of SrO for CaO on the properties of the bioactive glass S53P4 was studied. Thermal analysis and hot stage microscopy were utilized to measure the thermal properties of the glasses. The in vitro bioactivity and solubility was measured by immersing the glasses in simulated body fluid for 6 h to 1 week. The formation of silica rich and hydroxyapatite layers was assessed from FTIR spectra analysis and SEM images of the glass surface. Increasing substitution of SrO for CaO decreased all characteristic temperatures and led to a slightly stronger glass network. The initial glass dissolution rate increased with SrO content. Hydroxyapatite layer was formed on all glasses but on the SrO containing glasses the layer was thinner and contained also strontium. The results suggest that substituting SrO for CaO in S53P4 glass retards the bioactivity. However, substitution greater than 10 mol% allow for precipitation of a strontium substituted hydroxyapatite layer.

  12. A 3P-3W UPQC with Scott-Connected Transformer for 3P-4W Distribution System

    Directory of Open Access Journals (Sweden)

    PAL Yash

    2011-05-01

    Full Text Available In this paper, a new topology is developed for a three-phase four-wire (3P4W distribution system utilizing a scott-transformer supported three-legs VSIs based three-phase three-wire (3P3W Unified Power Quality Conditioner (UPQC.In this proposed topologythe neutral point of the star connected transformer, used for the connection of series active power filter (APF of 3P3W UPQC, is utilized as a fourth wire for 3P4W distribution system. The scott-connected transformer is connected near the load to compensatethe neutral current that may flow toward the neutral point of the series transformer of series APF. For the mitigation of different power quality(PQ problems a control technique based on the combination of unit template technique(UTT and power balancetheory(PBTis used for the control of UPQC. In this control scheme of UPQC, the current/voltage control is applied over the fundamental supply currents/voltages instead of fast changing APFs currents/voltages, there by reducing the computational delay and the required sensors. The performance of the proposed topology ofUPQC is analyzed through simulations results using MATLAB software with its Simulink and Power System Block set toolboxes.

  13. Cutaneous and Labyrinthine Tolerance of Bioactive Glass S53P4 in Mastoid and Epitympanic Obliteration Surgery: Prospective Clinical Study

    Directory of Open Access Journals (Sweden)

    Daniele Bernardeschi

    2015-01-01

    Full Text Available Objective. To evaluate the cutaneous and the inner ear tolerance of bioactive glass S53P4 when used in the mastoid and epitympanic obliteration for chronic otitis surgery. Material and Methods. Forty-one cases have been included in this prospective study. Cutaneous tolerance was clinically evaluated 1 week, 1 month, and 3 months after surgery with a physical examination of the retroauricular and external auditory canal (EAC skin and the presence of otalgia; the inner ear tolerance was assessed by bone-conduction hearing threshold 1 day after surgery and by the presence of vertigo or imbalance. Results. All surgeries but 1 were uneventful: all patients maintained the preoperative bone-conduction hearing threshold except for one case in which the round window membrane was opened during the dissection of the cholesteatoma in the hypotympanum and this led to a dead ear. No dizziness or vertigo was reported. Three months after surgery, healing was achieved in all cases with a healthy painless skin. No cases of revision surgery for removal of the granules occurred in this study. Conclusion. The bioactive glass S53P4 is a well-tolerated biomaterial for primary or revision chronic otitis surgery, as shown by the local skin reaction which lasted less than 3 months and by the absence of labyrinthine complications.

  14. Expansion joints for LMFBR

    International Nuclear Information System (INIS)

    Dzenus, M.; Hundhausen, W.; Jansing, W.

    1980-01-01

    This discourse recounts efforts put into the SNR-2 project; specifically the development of compensation devices. The various prototypes of these compensation devices are described and the state of the development reviewed. Large Na (sodium)-heat transfer systems require a lot of valuable space if the component lay-out does not include compensation devices. So, in order to condense the spatial requirement as much as possible, expansion joints must be integrated into the pipe system. There are two basic types to suit the purpose: axial expansion joints and angular expansion joints. The expansion joints were developed on the basis of specific design criteria whereby differentiation is made between expansion joints of small and large nominal diameter. Expansion joints for installation in the sodium-filled primary piping are equipped with safety bellows in addition to the actual working bellows. Expansion joints must be designed and mounted in a manner to completely withstand seismic forces. The design must exclude any damage to the bellows during intermittent operations, that is, when sodium is drained the bellows' folds must be completely empty; otherwise residual solidified sodium could destroy the bellows when restarting. The expansion joints must be engineered on the basis of the following design data for the secondary system of the SNR project: working pressure: 16 bar; failure mode pressure: 5 events; failure mode: 5 sec., 28.5 bar, 520 deg. C; working temperature: 520 deg. C; temperature transients: 30 deg. C/sec.; service life: 200,000 h; number of load cycles: 10 4 ; material: 1.4948 or 1.4919; layer thickness of folds: 0.5 mm; angular deflection (DN 800): +3 deg. C or; axial expansion absorption (DN 600): ±80 mm; calculation: ASME class. The bellows' development work is not handled within this scope. The bellows are supplied by leading manufacturers, and warrant highest quality. Multiple bellows were selected on the basis of maximum elasticity - a property that has a substantial effect on the reliability of the entire system. Later on, a number of experimental programs will be presented and results of previous trials discussed. (author)

  15. Vibrating fuel grapple. [LMFBR

    Science.gov (United States)

    Chertock, A.J.; Fox, J.N.; Weissinger, R.B.

    A reactor refueling method is described which utilizes a vibrating fuel grapple for removing spent fuel assemblies from a reactor core. It incorporates a pneumatic vibrator in the grapple head which allows additional withdrawal capability without exceeding the allowable axial force limit. The only moving part in the vibrator is a steel ball, pneumatically driven by a gas, such as argon, around a track, with centrifugal force created by the ball being transmitted through the grapple to the assembly handling socket.

  16. The LMFBR safety case

    International Nuclear Information System (INIS)

    Smith, D.

    1990-01-01

    The main objective of this report is to review the present status of the safety case for the liquid metal cooled fast reactor (FBR). A particular emphasis is placed on activities in Europe where the FBR has been progressively developed for many years during which time systems have passed from small experimental plants to the 1200 MWe SPX-1. The FBR has been found to be an easily controlled plant with low impact on the environment and low dose rates to operational personnel. Aspects of reactor design and associated R and D that are required for FBRs to be licensed and the progress made to meet these requirements are described. Fault conditions in the credible range can be dealt with safely, the FBR having several advantageous characteristics which assist safety. Also measures are foreseen to mitigate potential consequences of more severe but improbable accidents. This study sponsored by the Commission of the European Communities was carried out by Colenco Ltd in vlose collaboration with the Safety Working Group (SWG) which is a subgroup of the CEC Fast Reactor Coordinating Committee (FRCC)

  17. LMFBR core materials

    International Nuclear Information System (INIS)

    Roberts, J.T.A

    1981-01-01

    This paper discusses initial fuel and core designs that are conservative, emphasizing high reliability at the expense of breeding ration and doubling time. The progression in design improvements to better doubling time, plutonium inventory requirements, and power density are shown. The recent progress in advanced oxide fuel, cladding, and duct development is reported. Breeding ratios and compound system doubling times are computed for both the conventional homogeneous and alternative heterogeneous core configurations. Results are summarized and it is shown that both carbide and metal cores can achieve breeding ratios in the range of 1.5 to 1.6 versus 1.45 for oxide; the carbide and metal cores can achieve 10 year doubling times, which translate into millions of dollars savings in fuel cycle costs. Carbide fuel development is being continued at a modest level to provide backup to the mixed oxide design

  18. PINEX-2 experiment: concept verification of an inherent shutdown mechanism for HCDA's

    International Nuclear Information System (INIS)

    Porten, D.R.; Padilla, A. Jr.; Baars, R.E.

    1979-07-01

    PINEX-2 was a dual-objective experiment to continue development of the Pinhole Imaging (PINEX) system for monitoring fuel motion, and to further demonstrate the feasibility of internal fuel motion as a mechanism for mitigating the consequences of hypothetical LMFBR accidents. A special fuel pin with a pre-fabricated central hole in the fuel, insulator, and reflector was pre-irradiated in the General Electric Test Reactor and subjected to a simulated 5$/sec transient overpower excursion in the Transient Reactor Test (TREAT) facility. Approximately 10 grams of molten fuel were ejected upward from the fuel region into the reflector and fission gas plenum

  19. Engineering Physics Division integral experiments and their analyses

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    Integral experiments are performed as part of the Engineering Physics Division's on-going research in the development and application of radiation shielding methods. Integral experiments performed at the Oak Ridge Electron Linear Accelerator (ORELA) under the Division's Magnetic Fusion program are designed to provide data against which ORNL and all other organizations involved in shielding calculations for fusion devices can test their calculational methods and interaction data. The Tower Shielding Facility (TSF) continues to be the primary source of integral data for fission reactor shielding design. The experiments performed at the TSF during the last few years have been sponsored by the Gas Cooled Fast Reactor (GCFR) program. During this report period final documentation was also prepared for the remaining LMFBR shielding experiments, including an examination of streaming through annular slits and measurement of secondary gamma-ray production in reinforced concrete

  20. Analysis of the OPERA-15 two-dimensional voiding experiment using the SAS4A code

    International Nuclear Information System (INIS)

    Briggs, L.L.

    1984-01-01

    The SAS4A accident analysis code is a tool for evaluating consequences of accidents in Liquid Metal Fast Breeder Reactors (LMFBR). It incorporates models for describing coolant voiding, fuel pin swelling and disruption, cladding motion, heat transfer, and reactivity feedback. As part of the code verification effort, SAS4A is used to analyze both in-pile and out-of-pile safety experiments. Such an experiment is the fifteen-pin Out-of-Pile Expulsion and Reentry Apparatus (OPERA) test run at Argonne National Laboratory. This test uses a fifteen-pin triangular-shaped bundle of simulant fuel pins to demonstrate two-dimensional voiding behavior in a LMFBR subassembly during a Loss-of-Flow (LOF) accident. The experiment has been analyzed using SAS4A for two reasons; further code validation, and evaluation of the limitations of the one-dimensional SAS4A sodium voiding model in accident analysis. A comparison of experimental data and code results shows that the SAS4A model follows the experiment quite well during times when the experiment is behaving in a one-dimensional fashion (prior to start of voiding and after full radial voiding has been established). The code does not do as well during the period right after voiding initiation when the void is propagating radially and, to a lesser extent, axially

  1. Coordination Behavior of [Cp''2Zr(η1:1-P4)] towards Different Lewis Acids.

    Science.gov (United States)

    Seitz, Andreas E; Vogel, Ulf; Eberl, Miriam; Eckhardt, Maria; Balázs, Gábor; Peresypkina, Eugenia V; Bodensteiner, Michael; Zabel, Manfred; Scheer, Manfred

    2017-08-01

    A detailed method for the preparation of [Cp'' 2 Zr(η 1:1 -P 4 )] (1) is presented. The coordination behavior of 1 towards Lewis acidic transition metal complexes of tungsten, manganese, and iron, respectively, and main group compounds (AlMe 3 , AlEt 3 ) was investigated in detail by computational and experimental studies. In doing so, a series of unprecedented complexes with different coordination modes and multiple coordination numbers of the tetraphosphabicyclo[1.1.0]butane framework were synthesized. All products, as well as the starting materials, were comprehensively characterized by NMR spectroscopy, mass spectrometry, elemental analysis, and single crystal X-ray structural analysis. © 2017 Wiley-VCH Verlag GmbH & Co. KGaA, Weinheim.

  2. A novel method for immobilization of Co tetraphenylporphyrins on P(4VP-co-St)/SiO 2: Efficient catalysts for aerobic oxidation of ethylbenzenes

    Science.gov (United States)

    Wang, Ruixin; Gao, Baojiao; Jiao, Weizhou

    2009-01-01

    In this paper, poly(4vinylpyridine-co-styrene) (P(4VP-co-St)) was grafted on silica gel particles in the manner of "grafting from", and the grafting particle P(4VP-co-St)/SiO 2 was gained. The grafting particle P(4VP-co-St)/SiO 2 is a novel kind of supports for immobilizing metalloporphyrin catalysts. Then, the immobilization of cobalt tetraphenylporphyrin (CoTPP) on the supports P(4VP-co-St)/SiO 2 was carried out via the axial coordination reaction between CoTPP and the pyridine groups of the grafted P(4VP-co-St), resulting in the heterogenised catalysts CoTPP-P(4VP-co-St)/SiO 2. The synthesized catalysts were characterized by FTIR and the axial coordination process between CoTPP and the grafted P(4VP-co-St) was confirmed by UV-vis. The effects of various factors on the immobilization reaction of CoTPP were studied in detail. Finally, the catalytic performance of CoTPP-P(4VP-co-St)/SiO 2 in the catalytic oxidation process of ethyl benzene was investigated. The experimental results show that the axial coordination reaction is a very easy and novel method for favorably immobilizing CoTPP onto the P(4VP-co-St)/SiO 2 surfaces. During the immobilization process of CoTPP on P(4VP-co-St)/SiO 2, the most bonding amount of CoTPP (0.19 g/g) is obtained under the lower temperature (5 °C) and the higher concentration of CoTPP(6.0 mg/ml) lasting 4 h. Moreover, the supported catalyst CoTPP-P(4VP-co-St)/SiO 2 can effectively activate the dioxygen, and obviously catalyze the transform of ethylbenzene into acetophenone. So it exhibits the fine catalytic activity.

  3. Role of post-translational modifications at the β-subunit ectodomain in complex association with a promiscuous plant P4-ATPase

    DEFF Research Database (Denmark)

    Costa, Sara; Marek, Magdalena; Axelsen, Kristian Buhl

    2016-01-01

    P-type ATPases of subfamily IV (P4-ATPases) constitute a major group of phospholipid flippases that form heteromeric complexes with members of the Cdc50 (cell division control 50) protein family. Some P4-ATPases interact specifically with only one β-subunit isoform, whereas others are promiscuous...

  4. Fast-electron-impact study on excitations of 4p, 4s, and 3d electrons of krypton

    International Nuclear Information System (INIS)

    Yuan Zhensheng; Zhu Linfan; Liu Xiaojing; Li Wenbin; Cheng Huadong; Xu Kezun; Zhong Zhiping

    2002-01-01

    Absolute optical oscillator strength densities for the excitations of the electrons 4p, 4s, and 3d have been measured. Their absolute optical oscillator strengths have also been obtained. An enhancement above the 4p ionization threshold in the photoabsorption spectrum was assigned as a delayed maximum which arises from the photoionization process of 4p→εd according to present Dirac-Slater calculation. In the energy region of 4s autoionization, we have observed several features that are absent in previous fast-electron-impact work, but exist in optical measurements. We clarify this discrepancy here. Two Rydberg series of optically forbidden transitions, i.e., 4s -1 ns( 1 S) (n=5,6,7) and 4s -1 nd( 1 D) (n=4,5,6,7) have been observed when the spectrometer worked at conditions with larger momentum transfers, namely, K 2 =0.23 a.u. and 0.67 a.u. Furthermore, the absolute optical oscillator strengths for the 3d excitation have been obtained

  5. Monte Carlo Calculation Of HPGe GEM 15P4 Detector Efficiency In The 59 - 2000 keV Energy Range

    International Nuclear Information System (INIS)

    Trinh Hoai Vinh; Pham Nguyen Thanh Vinh; Hoang Ba Kim; Vo Xuan An

    2011-01-01

    A precise model of a 15% relative efficiency p-type HPGe GEM 15P4 detector was created for peak efficiency curves determination using the MCNP5 code developed by The Los Alamos Laboratory. The dependence of peak efficiency on distance from the source to detector was also investigated. That model was validated by comparing experimental and calculated results using six standard point sources including 133 Ba, 109 Cd, 57 Co, 60 Co, 22 Na and 65 Zn. The sources used for more simulating are 241 Am, 75 Se, 113 Sn, 85 Sr, 54 Mn, 137 Cs, 56 Co, 94 Nb, 111 In, 139 Ce, 228 Th, 243 Am, 154 Eu, 152 Eu and 88 Y according to IAEA-TECDOC-619 document. All these sources have the same geometry. The ratio of the experimental efficiencies to calculated ones are higher than 0.94. This result indicates that our simulation program based on MCNP5 code is good enough for later studies on this HPGe spectrometer which is located in Nuclear Physics Laboratory at HCMC University of Pedagogy. (author)

  6. A novel cobalt(II)-selective potentiometric sensor based on p-(4-n-butylphenylazo)calix[4]arene.

    Science.gov (United States)

    Kumar, Pankaj; Shim, Yoon-Bo

    2009-01-15

    A new poly(vinyl chloride)-based membranes containing p-(4-n-butylphenylazo)calix[4]arene (I) as an electroactive material along with sodiumtetraphenylborate (NaTPB), and dibutyl(butyl)phosphonate in the ratio 10:100:1:200 (I:DBBP:NaTPB:PVC) (w/w) was used to fabricate a new cobalt(II)-selective sensor. It exhibited a working concentration range of 9.2 x 10(-6) to 1.0 x 10(-1)M, with a Nernstian slope of 29.0+/-1.0 mV/decade of activity and the response time of 25s. This sensor shows the detection limit of 4.0 x 10(-6)M. Its potential response remains unaffected of pH in the range, 4.0-7.2, and the cell assembly can be used successfully in partially non-aqueous medium (up to 10%, v/v) without significant change in the slope of working concentration range. The sensor has a lifetime of about 3 months and exhibits excellent selectivity over a number of mono-, bi-, and tri-valent cations including alkali, alkaline earth metal, heavy and transition metal ions. It can be used as an indicator electrode for the end point determination in the potentiometric titration of cobalt ions against ethylenediaminetetraacetic acid (EDTA) as well as for the determination of cobalt ion concentration in real samples.

  7. Phase structures of the black Dp-D(p+4)-brane system in various ensembles II: electrical and thermodynamic stability

    International Nuclear Information System (INIS)

    Xiao, Zhiguang; Zhou, Da

    2015-01-01

    By incorporating the electrical stability condition into the discussion, we continue the study on the thermodynamic phase structures of the Dp-D(p+4) black brane in GG, GC, CG, CC ensembles defined in our previous paper http://dx.doi.org/10.1007/JHEP07(2015)134. We find that including the electrical stability conditions in addition to the thermal stability conditions does not modify the phase structure of the GG ensemble but puts more constraints on the parameter space where black branes can stably exist in GC, CG, CC ensembles. In particular, the van der Waals-like phase structure which was supposed to be present in these ensembles when only thermal stability condition is considered would no longer be visible, since the phase of the small black brane is unstable under electrical fluctuations. However, the symmetry of the phase structure by interchanging the two kinds of brane charges and potentials is still preserved, which is argued to be the result of T-duality.

  8. Constituents of a hit parade: Questioning democracy and listener participation in P4 i P1’s Det elektriske barometer

    Directory of Open Access Journals (Sweden)

    Mette Simonsen Abildgaard

    2014-12-01

    Full Text Available Due to their historically inaccessible nature, public service broadcasters’ media archives have lent themselves primarily to internal refl ection while historical contextualisation of the cultural heritage in these archives has been broadcasters’ prerogative. In this study, digitised material from the Danish youth radio programme P4 i P1’s Det elektriske barometer forms the basis for an experiment into how access to digital archives can inform humanities scholarship. We argue that one important implication of the new digital archives is that they enable approaches independent of broadcasters’ own narratives since they off er the possibility for autonomous study of large quantities of material. The character of listener participation in Det elektriske barometer, which had the slogan ‘the listener-determined hit parade’, is approached from a micro-, meso-, and macro-level employing Carpentier’s concept of participation (2011b, to explore how diff erent approaches to digital archives can provide new answers to media’s self-presentation.

  9. PEMBANGUNAN DAERAH DAN PENANGGULANGAN KEMISKINAN (Studi Kasus Implementasi Proyek Pembinaan Peningkatan Pendapatan Petani Dan Nelayan Kecil (P4K di Kabupaten Jombang

    Directory of Open Access Journals (Sweden)

    Affandi - -

    2012-05-01

    Full Text Available ABSTRAK   Pentingnya program pemberdayaan dalam rangka menanggulangi kemiskian, salah satunya Program P4K adalah agar lingkaran setan kemiskinan dapat diputus sehingga kemakmuran dan implementasi pembangunan menampakkan hasil yang nyata. Dalam pembangunan di Indonesia, penanggulangan kemiskinan dan pemberdayaan telah dijadikan titik sentral, dimana program tersebut dijalankan secara serentak dan terkoordinir di daerah-daerah yang dikenal dengan kegiatan Pembinaan Peningkatan Pendapatan Petani dan Nelayan Kecil (P4K. Permasalahan dalam penelitian ini adalah bagaimana implementasi kebijakan pembangunan Pemerintah Daerah (Program P4K dilaksanakan dalam rangka penanggulangan kemiskinan dan bagaimana pembangunan dalam memberdayakan petani dapat meningkatkan pemahaman dan pengetahuan petani serta upaya-upaya dan hambatan-hambatan apa saja yang dihadapi Pemerintah dalam melaksanakan Program P4 dalam rangka penanggulangan kemiskinan di Kabupaten Jombang. Tujuan penelitian ini adalah: (1 mendeskripsikan dan menganalisis implementasi kebijakan pembangunan (Program P4K dalam rangka penanggulangan kemiskinan; (2 mendeskripsikan dan menganalisis pembangunan dalam memberdayakan petani sehingga dapat meningkatkan pemahaman dan pengetahuan petani, serta mengetahui upaya-upaya dan hambatan-hambatan pelaksanaan Program P4K dalam rangka penanggulangan kemiskinan di Kabupaten Jombang. Dengan menggunakan pendekatan kualitatif, hasil penelitian ini disimpulkan bahwa, Program P4K sebagai upaya pemberdayaan kaum miskin pedesaan dengan pemberian bantuan modal, banyak dimanfaatkan oleh masyarakat desa untuk membuka usaha baru dan industri kecil lokal. Keberhasilan Program P4K di Kabupaten Jombang memiliki ciri khas tersendiri, yaitu Program P4K banyak diikuti kaum perempuan petani, sehingga kemampuan petani dalam memanfaatkan dan menyerap dana bantuan P4K sangat tinggi ditunjukkan banyak KPK yang antri untuk memperoleh bantuan atau peningkatan dana bantuan. Orientasi

  10. Synthesis and preliminary evaluation of [18F]FEtP4A, a promising PET tracer for mapping acetylcholinesterase in vivo

    International Nuclear Information System (INIS)

    Zhang Mingrong; Tsuchiyama, Akio; Haradahira, Terushi; Furutsuka, Kenji; Yoshida, Yuichiro; Junko Noguchi, Takayo Kida; Irie, Toshiaki; Suzuki, Kazutoshi

    2002-01-01

    N-[ 18 F]Fluoroethyl-4-piperidyl acetate ([ 18 F]FEtP4A), an analog of [ 11 C]MP4A for mapping brain acetylcholineseterase (AchE) activity, was prepared by reacting 4-piperidyl acetate (P4A) with [ 18 F]fluoroethyl bromide ([ 18 F]FEtBr) using a newly developed automated system. Preliminary evaluation showed that the initial uptake of [ 18 F]FEtP4A in the mouse brain was > 8% injected dose/g tissue. The distribution pattern of [ 18 F]FEtP4A in the brain was striatum>cerebral cortex>cerebellum within 10-120 min post-injection, which reflected the distribution rank pattern of AchE activity in the brain. Moreover, chemical analysis of in vivo radioactive metabolites in the mouse brain indicated that 83% of [ 18 F]FEtP4A was hydrolyzed to N-[ 18 F]fluoroethyl-4-piperidinol ([ 18 F]FEtP4OH) after 1 min intravenous injection. From these results, [ 18 F]FEtP4A may become a promising PET tracer for mapping the AchE in vivo

  11. Phage phi 29 regulatory protein p4 stabilizes the binding of the RNA polymerase to the late promoter in a process involving direct protein-protein contacts.

    Science.gov (United States)

    Nuez, B; Rojo, F; Salas, M

    1992-12-01

    Transcription from the late promoter, PA3, of Bacillus subtilis phage phi 29 is activated by the viral regulatory protein p4. A kinetic analysis of the activation process has revealed that the role of protein p4 is to stabilize the binding of RNA polymerase to the promoter as a closed complex without significantly affecting further steps of the initiation process. Electrophoretic band-shift assays performed with a DNA fragment spanning only the protein p4 binding site showed that RNA polymerase could efficiently retard the complex formed by protein p4 bound to the DNA. Similarly, when a DNA fragment containing only the RNA polymerase-binding region of PA3 was used, p4 greatly stimulated the binding of RNA polymerase to the DNA. These results strongly suggest that p4 and RNA polymerase contact each other at the PA3 promoter. In the light of current knowledge of the p4 activation mechanism, we propose that direct contacts between the two proteins participate in the activation process.

  12. The 4s24p3-4s4p4 transition in AsI-like AgXV

    International Nuclear Information System (INIS)

    Dong Chenzhong; Zhao Jinbao

    1992-01-01

    Some terms of the 4s 4p 4 configuration in RuXII, RhXIII and PdXIV ions can be improved and all the energy values of the configuration in AgXV can be predicted theoretically by means of a configuration-interaction ab initio analysis for the level structure of the 4s 4p 4 configuration along the AsI sequence of KrIV-AgXV ions. Calculations of the wavelengths and oscillator strenghts are presented for the 4s 2 4p 3 -4s 4p 4 transition in AgXV. (orig.)

  13. Breeders: operational experience with fast power reactors in five states - more intensive German-French breeder cooperation

    International Nuclear Information System (INIS)

    Hueper, R.

    1978-01-01

    In the past year contracts have been signed and implemented for German-French cooperation in LMFBR development and commercialization. - The first German nuclear power station with a sodium cooled fast reactor, KNK II in Karlsruhe, is going into operation. - Construction of the prototype SNR 300 at Kalkar (Lower Rhine) is slowing down awaiting a decision of the German Federal Constitutional Court. - On the international level, remarkable experience in the operation of fast power reactors has accumulated. - Possible fuel cycle alternatives are being evaluated by an international committee. (orig.) [de

  14. Sodium boiling and mixed oxide fuel thermal behavior in FBR undercooling transients; W-1 SLSF experiment results

    International Nuclear Information System (INIS)

    Henderson, J.M.; Wood, S.A.; Knight, D.D.

    1981-01-01

    The W-1 Sodium Loop Safety Facility (SLSF) Experiment was conducted to study fuel pin heat release characteristics during a series of LMFBR Loss-of-Piping Integrity (LOPI) transients and to investigate a regime of coolant boiling during a second series of transients at low, medium and high bundle power levels. The LOPI transients produced no coolant boiling and showed only small changes in coolant temperatures as the test fuel microstructure changed from a fresh, unrestructured to a low burnup, restructured condition. During the last of seven boiling transients, intense coolant boiling produced inlet flow reversal, cladding dryout and moderate cladding melting

  15. MiR-30e suppresses proliferation of hepatoma cells via targeting prolyl 4-hydroxylase subunit alpha-1 (P4HA1) mRNA

    International Nuclear Information System (INIS)

    Feng, Guoxing; Shi, Hui; Li, Jiong; Yang, Zhe; Fang, Runping; Ye, Lihong; Zhang, Weiying; Zhang, Xiaodong

    2016-01-01

    Aberrant microRNA expression has been shown to be characteristic of many cancers. It has been reported that the expression levels of miR-30e are decreased in liver cancer tissues. However, the role of miR-30e in hepatocellular carcinoma remains poorly understood. In the present study, we investigated the significance of miR-30e in hepatocarcinogenesis. Bioinformatics analysis reveals a putative target site of miR-30e in the 3′-untranslated region (3′UTR) of prolyl 4-hydroxylase subunit alpha-1 (P4HA1) mRNA. Moreover, luciferase reporter gene assays verified that miR-30e directly targeted 3′UTR of P4HA1 mRNA. Then, we demonstrated that miR-30e was able to reduce the expression of P4HA1 at the levels of mRNA and protein using reverse transcription-polymerase chain reaction and Western blot analysis. Enforced expression of miR-30e suppressed proliferation of HepG2 cells by 5-ethynyl-2-deoxyuridine (EdU) assay and reduced colony formation of these cells by colony formation analysis. Conversely, anti-miR-30e enhanced the proliferation of hepatoma cells in vitro. Interestingly, the ectopic expression of P4HA1 could efficiently rescue the inhibition of cell proliferation mediated by miR-30e in HepG2 cells. Meanwhile, silencing of P4HA1 abolished the anti-miR-30e-induced proliferation of cells. Clinically, quantitative real-time PCR showed that miR-30e was down-regulated in liver tumor tissues relative to their peritumor tissues. The expression levels of miR-30e were negatively correlated to those of P4HA1 mRNA in clinical liver tumor tissues. Thus, we conclude that miR-30e suppresses proliferation of hepatoma cells through targeting P4HA1 mRNA. Our finding provides new insights into the mechanism of hepatocarcinogenesis. - Highlights: • P4HA1 is a novel target gene of miR-30e. • P4HA1 is increased in clinical HCC tissues. • MiR-30e is negatively correlated with P4HA1 in clinical HCC tissues. • MiR-30e suppresses the proliferation of HCC cells through

  16. MiR-30e suppresses proliferation of hepatoma cells via targeting prolyl 4-hydroxylase subunit alpha-1 (P4HA1) mRNA

    Energy Technology Data Exchange (ETDEWEB)

    Feng, Guoxing [State Key Laboratory of Medicinal Chemical Biology, Department of Cancer Research, College of Life Sciences, Nankai University, Tianjin (China); Shi, Hui [State Key Laboratory of Medicinal Chemical Biology, Department of Biochemistry, College of Life Sciences, Nankai University, Tianjin (China); Li, Jiong; Yang, Zhe [State Key Laboratory of Medicinal Chemical Biology, Department of Cancer Research, College of Life Sciences, Nankai University, Tianjin (China); Fang, Runping; Ye, Lihong [State Key Laboratory of Medicinal Chemical Biology, Department of Biochemistry, College of Life Sciences, Nankai University, Tianjin (China); Zhang, Weiying, E-mail: zhwybao@nankai.edu.cn [State Key Laboratory of Medicinal Chemical Biology, Department of Cancer Research, College of Life Sciences, Nankai University, Tianjin (China); Zhang, Xiaodong, E-mail: zhangxd@nankai.edu.cn [State Key Laboratory of Medicinal Chemical Biology, Department of Cancer Research, College of Life Sciences, Nankai University, Tianjin (China)

    2016-04-08

    Aberrant microRNA expression has been shown to be characteristic of many cancers. It has been reported that the expression levels of miR-30e are decreased in liver cancer tissues. However, the role of miR-30e in hepatocellular carcinoma remains poorly understood. In the present study, we investigated the significance of miR-30e in hepatocarcinogenesis. Bioinformatics analysis reveals a putative target site of miR-30e in the 3′-untranslated region (3′UTR) of prolyl 4-hydroxylase subunit alpha-1 (P4HA1) mRNA. Moreover, luciferase reporter gene assays verified that miR-30e directly targeted 3′UTR of P4HA1 mRNA. Then, we demonstrated that miR-30e was able to reduce the expression of P4HA1 at the levels of mRNA and protein using reverse transcription-polymerase chain reaction and Western blot analysis. Enforced expression of miR-30e suppressed proliferation of HepG2 cells by 5-ethynyl-2-deoxyuridine (EdU) assay and reduced colony formation of these cells by colony formation analysis. Conversely, anti-miR-30e enhanced the proliferation of hepatoma cells in vitro. Interestingly, the ectopic expression of P4HA1 could efficiently rescue the inhibition of cell proliferation mediated by miR-30e in HepG2 cells. Meanwhile, silencing of P4HA1 abolished the anti-miR-30e-induced proliferation of cells. Clinically, quantitative real-time PCR showed that miR-30e was down-regulated in liver tumor tissues relative to their peritumor tissues. The expression levels of miR-30e were negatively correlated to those of P4HA1 mRNA in clinical liver tumor tissues. Thus, we conclude that miR-30e suppresses proliferation of hepatoma cells through targeting P4HA1 mRNA. Our finding provides new insights into the mechanism of hepatocarcinogenesis. - Highlights: • P4HA1 is a novel target gene of miR-30e. • P4HA1 is increased in clinical HCC tissues. • MiR-30e is negatively correlated with P4HA1 in clinical HCC tissues. • MiR-30e suppresses the proliferation of HCC cells through

  17. Recent operating experiences and programs at EBR-II

    International Nuclear Information System (INIS)

    Lentz, G.L.

    1984-01-01

    Experimental Breeder Reactor No. II (EBR-II) is a pool-type, unmoderated, sodium-cooled reactor with a design power of 62.5 MWt and an electrical generation capability of 20 MW. It has been operated by Argonne National Laboratory for the US government for almost 20 years. During that time, it has operated safely and has demonstrated stable operating characteristics, high availability, and excellent performance of its sodium components. The 20 years of operating experience of EBR-II is a valuable resource to the nuclear community for the development and design of future LMFBR's. Since past operating experience has been extensively reported, this report will focus on recent programs and events

  18. Role of post-translational modifications at the β-subunit ectodomain in complex association with a promiscuous plant P4-ATPase.

    Science.gov (United States)

    Costa, Sara R; Marek, Magdalena; Axelsen, Kristian B; Theorin, Lisa; Pomorski, Thomas G; López-Marqués, Rosa L

    2016-06-01

    P-type ATPases of subfamily IV (P4-ATPases) constitute a major group of phospholipid flippases that form heteromeric complexes with members of the Cdc50 (cell division control 50) protein family. Some P4-ATPases interact specifically with only one β-subunit isoform, whereas others are promiscuous and can interact with several isoforms. In the present study, we used a site-directed mutagenesis approach to assess the role of post-translational modifications at the plant ALIS5 β-subunit ectodomain in the functionality of the promiscuous plant P4-ATPase ALA2. We identified two N-glycosylated residues, Asn(181) and Asn(231) Whereas mutation of Asn(231) seems to have a small effect on P4-ATPase complex formation, mutation of evolutionarily conserved Asn(181) disrupts interaction between the two subunits. Of the four cysteine residues located in the ALIS5 ectodomain, mutation of Cys(86) and Cys(107) compromises complex association, but the mutant β-subunits still promote complex trafficking and activity to some extent. In contrast, disruption of a conserved disulfide bond between Cys(158) and Cys(172) has no effect on the P4-ATPase complex. Our results demonstrate that post-translational modifications in the β-subunit have different functional roles in different organisms, which may be related to the promiscuity of the P4-ATPase. © 2016 The Author(s). published by Portland Press Limited on behalf of the Biochemical Society.

  19. SU-G-IeP4-05: Experience with a Practical Approach to the Release of Radioactive Patients from Radiation Safety Isolation

    Energy Technology Data Exchange (ETDEWEB)

    Wendt, R; Erwin, W; Fisher, A; Jones, S; Jimenez, S; Wong, F; Jessop, A [UT MD Anderson Cancer Center, Houston, TX (United States)

    2016-06-15

    Purpose: The radioactive patient releases of the nuclear medicine department in a large cancer center were analyzed to compare the estimated doses to others to the regulatory limit and institutional targets and to gauge how onerous the patients’ instructions were. Methods: In-house software that implements the NUREG 1556 approach and further considers fellow travelers, children and pregnant women and members of the public following Siegel, et al., is used to calculate release timing and to provide patients with individualized instructions. A retrospective analysis of the 218 releases in 2015 that required instructions included all I-131 and Lu-177 treatments. Results: There were 87 male and 131 female patients. They were 45.5±16.5 (8-84) years old, weighed 83.3±21.8 kg and stood 168±10 cm tall with a body mass index of 29.3±6.7 kg/m2. 195 patients received 2.96±2.23 GBq of I-131-NaI for differentiated thyroid carcinoma and eight received 636±231 MBq of I-131-NaI for hyperthyroidism. There were eight administrations of 18.5 GBq of I-131-mIBG and seven administrations of 7.4 GBq of Lu-177-DOTATATE. The dose to the most exposed person was 1.67±1.05 (mode=0.60, median=1.15) mSv. The dose to a fellow traveler was 0.31±0.31 (mode=0.1, median=0.17) mSv. The dose to children and pregnant women was 0.51±0.34 (mode=1.0, median=0.42) mSv. The duration of isolation was 7.7±17.3 (mode=2, median=1.7) hours. The duration of sleeping alone was 60.4±127 (mode=0, median=15.5) hours. The time to delay traveling was 12.2±11 (mode=median=0) hours. The time to completely avoid children and pregnant women was 23.3±26.5 (0–254, mode=median=24) hours followed by limited contact for 20.6±68.1 (0–491, mode=median=0) hours. The time to avoid others (e.g., to wait to return to work) was 12.1±101 (0–1465, mode=median=0) hours. Conclusion: The estimated doses to others were often well below the limits set by regulation, 5 mSv, or prudent practice, 1 mSv. Most patients’ instructions were not hard to comply with.

  20. Thermodynamic and spectroscopic investigations of TMPyP4 association with guanine- and cytosine-rich DNA and RNA repeats of C9orf72.

    Science.gov (United States)

    Alniss, Hasan; Zamiri, Bita; Khalaj, Melisa; Pearson, Christopher E; Macgregor, Robert B

    2018-01-22

    An expansion of the hexanucleotide repeat (GGGGCC)n·(GGCCCC)n in the C9orf72 promoter has been shown to be the cause of Amyotrophic lateral sclerosis and frontotemporal dementia (ALS-FTD). The C9orf72 repeat can form four-stranded structures; the cationic porphyrin (TMPyP4) binds and distorts these structures. Isothermal titration calorimetry (ITC), and circular dichroism (CD) were used to study the binding of TMPyP4 to the C-rich and G-rich DNA and RNA oligos containing the hexanucleotide repeat at pH 7.5 and 0.1 M K + . The CD spectra of G-rich DNA and RNA TMPyP4 complexes showed features of antiparallel and parallel G-quadruplexes, respectively. The shoulder at 260 nm in the CD spectrum becomes more intense upon formation of complexes between TMPyP4 and the C-rich DNA. The peak at 290 nm becomes more intense in the c-rich RNA molecules, suggesting induction of an i-motif structure. The ITC data showed that TMPyP4 binds at two independent sites for all DNA and RNA molecules. For DNA, the data are consistent with TMPyP4 stacking on the terminal tetrads and intercalation. For RNA, the thermodynamics of the two binding modes are consistent with groove binding and intercalation. In both cases, intercalation is the weaker binding mode. These findings are considered with respect to the structural differences of the folded DNA and RNA molecules and the energetics of the processes that drive site-specific recognition by TMPyP4; these data will be helpful in efforts to optimize the specificity and affinity of the binding of porphyrin-like molecules. Copyright © 2018 Elsevier Inc. All rights reserved.

  1. Active acoustic leak detection for LMFBR steam generator. Pt. 5. Experiment for detection of bubbles using the SG full sector model

    International Nuclear Information System (INIS)

    Kumagai, Hiromichi

    1997-01-01

    In order to prevent the expansion of tube damages and to maintain structural safety in steam generators (SG) of fast breeder reactors (FBR), it is necessary to detect precisely and immediately the leakage of water from tubes of heat exchangers. Therefore, an active acoustic method, which detects the sound attenuation due to bubbles generated in the sodium-water reactions, it being developed. In this paper, the attenuation characteristics of sound attenuated by bubbles and influence of background noise are investigated experimentally by using an SG full sector model (diameter ratio about 1/1, height ratio about 1/7) simulating the actual SG. As an experimental result, the received sound attenuation for ten seconds was more than 10 dB from air bubble injection when injected bubble of 10 l/s (equivalence water leak rate about 10 g/s). The attenuation of sound are least affected by bubble injection position of heat exchanger tube bunch department. And the time was about 25 seconds till the sound attenuation became 10 dB in case of quantity of air bubble 1 l/s (equivalent water leak rate about 1 g/s). It is clarified that the background noise hardly influenced water leak detection performance as a result of having examined influence of background noise. (author)

  2. Natural circulation of sodium in a 37 electrically heated pin bundle: Results of the SCARLET-R experiments and application to decay heat removal in lmfbr fuel assemblies

    International Nuclear Information System (INIS)

    Olive, J.; Aubry, S.; Ribound, P.M.

    1987-01-01

    Natural convection tests were carried out on a 37 electrically heated pin bundle, SCARLET-R, which simulates a SUPER-PHENUX fissile sub-assembly. Temperature fields were measured in three axial planes. The axisymmetrical single phase tests revealed that temperatures are very sensitive to thermal conductivity of the pins. A good agreement between the result of the CAFCA-NA2 code and the test results was obtained, thanks to a correlation for the average conductivity of the bundle which was developed on theoretical bases and put into the code. Three-dimensional tests were also conducted and compared with calculations performed with the 3D code CAFCA-NA3. Axisymmetrical two-phase flow test in natural convection were defined and precalculated with a preliminary two-phase version of CAFCA-NA2. The test results, which were obtained in April, 1987 are analyzed and reported

  3. Effect of oestrus synchronization with PGF2α/eCG/hCG on luteal P4 synthesis in early pregnant gilts.

    Science.gov (United States)

    Szymanska, M; Morawska-Pucinska, E; Krawczynski, K; Kiewisz, J; Ziecik, A J; Blitek, A

    2014-12-01

    Administration of hormones to synchronize oestrus is a useful tool in animal breeding. However, exogenous ovarian stimulation may be detrimental to reproductive function. This study was aimed to examine whether an oestrus synchronization with PGF2α/eCG/hCG could affect luteal P4 synthesis in early pregnant gilts. Corpora lutea (CLs) were collected on days 9, 12 and 16 of pregnancy from gilts with natural (n = 16) and synchronized (n = 18) oestrus and analysed for (i) the expre-ssion of steroidogenic acute regulatory protein (StAR), cytochrome P450 family 11 subfamily A polypeptide (CYP11A1), and 3β-hydroxysteroid dehydrogenase (3βHSD); (ii) the concentration of P4 in the luteal tissue and blood; and (iii) the expression of luteinizing hormone receptors (LHR) and oestrogen receptors (ERα and ERβ). Additionally, the effect of LH on P4 secretion from CL slices collected from synchronized and naturally ovulated animals has been studied in vitro. PGF2α /eCG/hCG administration increased mRNA expression of StAR, CYP11A1, 3βHSD, and LHR on day 9 and CYP11A1 and LHR on day 12 of pregnancy compared with the control group (p gilts with hormonally induced oestrus compared with control animals. Blood serum levels of P4 were lower in synchronized than control gilts (p gilts (p gilts did not impair the expression of luteal P4 synthesis system, although decreased P4 concentration in the blood. © 2014 Blackwell Verlag GmbH.

  4. Integrated Analysis of PTEN and p4EBP1 Protein Expression as Predictors for pCR in HER2-Positive Breast Cancer.

    Science.gov (United States)

    Loibl, Sibylle; Darb-Esfahani, Silvia; Huober, Jens; Klimowicz, Alexander; Furlanetto, Jenny; Lederer, Bianca; Hartmann, Arndt; Eidtmann, Holger; Pfitzner, Berit; Fasching, Peter A; Tiemann, Katharina; Jackisch, Christian; Mehta, Keyur; von Minckwitz, Gunter; Untch, Michael; Denkert, Carsten

    2016-06-01

    The PI3K/AKT pathway and phosphatase and tensin homolog (PTEN) aberrations are common in breast cancer. We investigated the correlation between phosphatidylinositol-4,5-bisphosphate 3-kinase catalytic subunit alpha (PIK3CA), PTEN, p4EBP1 (phosphorylated E4 binding protein 1), and pathologic complete response (pCR) in patients receiving neoadjuvant therapy. We retrospectively evaluated PIK3CA, PTEN, and p4EBP1 protein expression in centrally HER2-positive patients (n = 181) who received epirubicin cyclophosphamide/trastuzumab followed by docetaxel/trastuzumab alone or concomitant/followed by capecitabine within the GeparQuattro study. PTEN was assessed using the automated quantitative immunofluorescence analysis and was analyzed as a dichotomic variable. p4EBP1 was assessed by immunohistochemistry and used as a continuous and dichotomic variable. p4EBP1 was available from 137, PTEN from 108, and PIK3CA genotype from 83 patients. Overall, the pCR rate in PTEN-low tumors was 27.6%, and in PTEN-high tumors, it was 57.1% (P = 0.010). pCR rates were not statistically different between PIK3CA wild-type and mutant (35% vs. 22%) or p4EBP1 IRS ≤ 4 and IRS > 4 (39% vs. 33%). pCR rate was 57.1% (8/14) in PTEN-high/PIK3CA wild-type and decreased to 15.4% in PTEN-low/PIK3CA-mutant tumors (P = 0.023). In multivariable analysis adjusted for baseline parameters, PTEN independently predicted pCR in the following cohorts: overall [OR, 7.54; 95% confidence interval (CI), 2.03-28.06; P = 0.003], PIK3CA wild-type (OR, 23.81; 95% CI, 1.75-324.05; P = 0.017), p4EBP1 IRS > 4 (OR, 11.53; 95% CI, 1.84-72.24; P = 0.009), and hormone receptor-positive (OR, 40.91; 95% CI, 2.93-570.44; P = 0.006). p4EBP1 was independently predictive for pCR in PIK3CA wild-type tumors (OR, 0.14; 95% CI, 0.03-0.78; P = 0.025). The study showed the potential role of PIK3CA genotype, PTEN, and p4EBP in predicting pCR after anthracycline-taxane-based chemotherapy and anti-HER2 treatment. Clin Cancer Res; 22

  5. Novel prodrug PRX-P4-003, selectively activated by gut enzymes, may reduce the risk of iatrogenic addiction and abuse.

    Science.gov (United States)

    Patil, Sandeep T; Bihovsky, Ron H; Smith, Steven A; Potter, William Z; Stella, Valentino J

    2018-03-02

    Prescription stimulants are vulnerable to oral and parenteral abuse. Intravenous forms of abuse may be most detrimental due to an enhanced risk of dependence, overdose, and infectious diseases. Our objective was to discover an orally active prodrug of a stimulant that would not be easily converted to its parent when injected, thus hindering intravenous abuse. Following an initial analysis of stimulant structures, the fencamfamine isomer [(-)-FCF; (N-ethyl-3-phenylbicyclo[2.2.1]heptan-2-amine)] was chosen as a parent drug due to its favorable biochemical properties. Subsequently, PRX-P4-003 {(-)-N-(Octadecanoyloxymethoxycarbonyl)-N-ethyl-3-phenylbicyclo[2.2.1]heptan-2-amine} qualified for further development. Experimental testing of PRX-P4-003 included radioligand binding assays, stability studies, and rodent pharmacokinetic and locomotor assays. Prodrug PRX-P4-003 is a pharmacologically inactive, hydrophobic compound, whereas its parent (-)-FCF is a dopamine reuptake inhibitor with weaker effects on norepinephrine reuptake (K i  = 0.07 and 0.80 μM, respectively). PRX-P4-003 is metabolized to (-)-FCF in simulated intestinal fluid (with pancreatin) but not in simulated gastric fluid (with pepsin). Finally, PRX-P4-003 shows a significant oral but no intravenous increase in locomotion, correlating with its pharmacokinetics by these different routes of administration. PRX-P4-003 is a novel prodrug stimulant enzymatically activated in the gut. Our data suggest a pancreatic, lipase-based mechanism of activation and as only 1% of this enzyme is found in the systemic circulation, PRX-P4-003 is unlikely to be bioactive if injected intravenously. Enzymatic release of (-)-FCF is needed prior to its systemic absorption, which may discourage oral abuse (e.g., by chewing). PRX-P4-003 is being developed for apathy in Alzheimer's disease and binge eating disorder. Copyright © 2018 Elsevier B.V. All rights reserved.

  6. The study of 3s3p4 configuration in the P-Sequence, Co X III - Ni X IV, by laser-produced plasmas

    International Nuclear Information System (INIS)

    Borges, F.O.; Cavalcanti, G.H.; Farias, E.E.; Trigueiros, A.G.

    2007-01-01

    Wavelengths from radiation of plasmas produced by a Nd:YAG/glass laser focused on target of Co and Ni have been recorded photographically in the region 240-600 A with a 3m normal incidence spectrograph. For this sequence (Co X III and Ni X IV) we have identified 13 new lines belonging to the array 3s 2 3p 3 -3s3p 4 and derived 7 new levels for the 3s3p 4 configuration. The classification was established by comparison of the relative intensities for the lines along the isoelectronic sequence, extrapolation, and Hartree-Fock calculation. (author)

  7. Instrumentation and Controls Division biennial progress report, September 1, 1974--September 1, 1976. Non-LMFBR programs

    International Nuclear Information System (INIS)

    Sadowski, G.S.

    1976-11-01

    Research progress and developments are reported in the areas of basic electronics, instruments, radiation monitoring, pulse counting and analysis, electronic engineering support for research facilities, automatic control and data acquisition, reactor instrumentation and controls, fuel reprocessing and shipping, process systems and instrumentation development, thermometry, instrumentation for reactor division experiments and test loops, environmental science studies, miscellaneous engineering studies, services, and developments, and maintenance

  8. Instrumentation and Controls Division biennial progress report, September 1, 1974--September 1, 1976. Non-LMFBR programs

    Energy Technology Data Exchange (ETDEWEB)

    Sadowski, G.S. (comp.)

    1976-11-01

    Research progress and developments are reported in the areas of basic electronics, instruments, radiation monitoring, pulse counting and analysis, electronic engineering support for research facilities, automatic control and data acquisition, reactor instrumentation and controls, fuel reprocessing and shipping, process systems and instrumentation development, thermometry, instrumentation for reactor division experiments and test loops, environmental science studies, miscellaneous engineering studies, services, and developments, and maintenance. (WHK)

  9. Fuel Coolant Thermal Interaction Project. Quarterly progress report No. 2, October 1, 1975--December 31, 1975. [LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Todreas, N.E.

    1976-03-01

    The objective of the work reported is to experimentally and analytically study the dominant mechanisms in fuel coolant thermal interactions which could lead to vapor explosions. The exploration of mechanisms is focused in two areas: (a) mechanisms responsible for fragmentation in molten metal droplet experiments (including assessment of the validity of the proposed spontaneous nucleation mechanism); and (b) thermal stress initiated fracture as a fragmentation mechanism. Work being performed in these areas is briefly described.

  10. Instrumentation and Controls Division annual progress report for period ending September 1, 1974. Non-LMFBR program

    Energy Technology Data Exchange (ETDEWEB)

    Sadowski, G.S. (comp.)

    1976-09-01

    Research projects are summarized under the following categories: (1) basic electronics development; (2) engineering support for research facilities; (3) pulse counting and analysis; (4) radiation detection and monitoring; (5) instrument development; (6) automatic control and data acquisition; (7) process systems and instrumentation development; (8) reactor instrumentation and controls; (9) fuel reprocessing and shipping; (10) standards laboratory; (11) instrumentation for reactor division experiments and test loops; (12) maintenance and service; (13) ecological science studies; and (14) administration and training. (WHK)

  11. Instrumentation and Controls Division annual progress report for period ending September 1, 1974. Non-LMFBR program

    International Nuclear Information System (INIS)

    Sadowski, G.S.

    1976-09-01

    Research projects are summarized under the following categories: (1) basic electronics development; (2) engineering support for research facilities; (3) pulse counting and analysis; (4) radiation detection and monitoring; (5) instrument development; (6) automatic control and data acquisition; (7) process systems and instrumentation development; (8) reactor instrumentation and controls; (9) fuel reprocessing and shipping; (10) standards laboratory; (11) instrumentation for reactor division experiments and test loops; (12) maintenance and service; (13) ecological science studies; and (14) administration and training

  12. Specific Mutations in Mammalian P4-ATPase ATP8A2 Catalytic Subunit Entail Differential Glycosylation of the Accessory CDC50A Subunit

    DEFF Research Database (Denmark)

    Vestergaard, Anna L.; Mikkelsen, Stine A.; Coleman, Jonathan A.

    2015-01-01

    P4-ATPases, or flippases, translocate phospholipids between the two leaflets of eukaryotic biological membranes. They are essential to the physiologically crucial phospholipid asymmetry and involved in severe diseases, but their molecular structure and mechanism are still unresolved. Here, we show...

  13. Genetic and serologic surveillance of rotavirus with P[8] and P[4] genotypes in feces from children in the city of Chihuahua, northern Mexico.

    Science.gov (United States)

    Contreras-Cordero, Juan F; Romo-Sáenz, César I; Menchaca-Rodríguez, Griselda E; Infante-Ramírez, Rocío; Villarreal-Treviño, Licet; Hernández-Luna, Carlos E; Rodríguez-Padilla, Cristina; Tamez-Guerra, Reyes S

    2015-12-01

    Rotavirus vaccine was developed using the most prominent G and P genotypes circulating in children population. Therefore, severe gastroenteritis has been reduced around the world. This study investigated the G and P rotavirus genotypes circulating in children from two hospitals in the city of Chihuahua, Mexico. Additionally, polyclonal antibodies against Rotavirus Wa strain were used to determine their homotypic and heterotypic reactivity to both P[8] and P[4] genotypes. G1, G2, and G3 VP7 genotypes and P[8] and P[4] VP4 genotypes were detected in common and uncommon combinations as well as mixed infectious. The predominant combination was G1P[8]. Phylogenetic analysis of VP4 gene revealed the presence of P[8]-1 and P[8]-3 lineages of P[8] genotype and P[4]-5 lineage of P[4] genotype. All but five G1P[8] rotavirus were detected by polyclonal anti-Rotavirus Wa strain. Mutation analysis revealed differences in three of the four neutralizing epitopes previously reported to VP8* subunit of VP4 protein. Results of this study offer insights over genetic variants of field rotavirus that could be detected in a homotypic and heterotypic way by antibodies elicited to rotavirus with P[8] genotype. [Int Microbiol 2016; 19(1):27-32]. Copyright© by the Spanish Society for Microbiology and Institute for Catalan Studies.

  14. A new family of clusters containing a silver-centered tetracapped [Ag@Ag4(μ3-P)4] tetrahedron, inscribed within a N12icosahedron.

    Science.gov (United States)

    Artem'ev, Alexander V; Bagryanskaya, Irina Yu; Doronina, Evgeniya P; Tolstoy, Peter M; Gushchin, Artem L; Rakhmanova, Mariana I; Ivanov, Alexander Yu; Suturina, Anastasiya O

    2017-09-26

    An unprecedented silver-centered P-tetracapped [Ag@Ag 4 (μ 3 -P) 4 ] tetrahedron inscribed within a N 12 icosahedral cage has been discovered in the novel family of luminescent clusters. The latter are easily self-assembled by reacting Ag I salts with tris(2-pyridyl)phosphine (Py 3 P).

  15. Insight from the draft genome of Dietzia cinnamea P4 reveals mechanisms of survival in complex tropical soil habitats and biotechnology potential

    NARCIS (Netherlands)

    Procopio, Luciano; Alvarez, Vanessa M.; Jurelevicius, Diogo A.; Hansen, Lars; Sorensen, Soren J.; Cardoso, Janine S.; Padula, Marcelo; Leitao, Alvaro C.; Seldin, Lucy; van Elsas, Jan Dirk

    The draft genome of Dietzia cinnamea strain P4 was determined using pyrosequencing. In total, 428 supercontigs were obtained and analyzed. We here describe and interpret the main features of the draft genome. The genome contained a total of 3,555,295 bp, arranged in a single replicon with an average

  16. Phosphate solubilization and promotion of maize growth by Penicillium oxalicum P4 and Aspergillus niger P85 in a calcareous soil.

    Science.gov (United States)

    Yin, Zhongwei; Shi, Fachao; Jiang, Hongmei; Roberts, Daniel P; Chen, Sanfeng; Fan, Bingquan

    2015-12-01

    Alternative tactics for improving phosphorus nutrition in crop production are needed in China and elsewhere, as the overapplication of phosphatic fertilizers can adversely impact agricultural sustainability. Penicillium oxalicum P4 and Aspergillus niger P85 were isolated from a calcareous soil in China that had been exposed to excessive application of phosphatic fertilizer for decades. Each isolate excreted a number of organic acids into, acidified, and solubilized phosphorus in a synthetic broth containing insoluble tricalcium phosphate or rock phosphate. Isolate P4, applied as a seed treatment, increased maize fresh mass per plant when rock phosphate was added to the calcareous soil in greenhouse pot studies. Isolate P85 did not increase maize fresh mass per plant but did significantly increase total phosphorus per plant when rock phosphate was added. Significant increases in 7 and 4 organic acids were detected in soil in association with isolates P4 and P85, respectively, relative to the soil-only control. The quantity and (or) number of organic acids produced by these isolates increased when rock phosphate was added to the soil. Both isolates also significantly increased available phosphorus in soil in the presence of added rock phosphate and effectively colonized the maize rhizosphere. Studies reported here indicate that isolate P4 is adapted to and capable of promoting maize growth in a calcareous soil. Plant-growth promotion by this isolate is likely due, at least in part, to increased phosphorus availability resulting from the excretion of organic acids into, and the resulting acidification of, this soil.

  17. Phosphate solubilization and promotion of maize growth in a calcareous soil by penicillium oxalicum P4 and aspergillus niger P85

    Science.gov (United States)

    Alternative tactics for improving phosphorus nutrition in crop production are needed in China and elsewhere as the over-application of phosphatic fertilizers can adversely impact agricultural sustainability. Penicillium oxalicum P4 and Aspergillus niger P85 were isolated from a calcareous soil in C...

  18. Cole-Carpenter syndrome-1 with a de novo heterozygous deletion in the P4HB gene in a Chinese girl: A case report.

    Science.gov (United States)

    Ouyang, Lixue; Yang, Fan

    2017-12-01

    Cole-Carpenter syndrome-1 (CLCRP1) is an independent osteogenesis imperfect (OI)-like disorder that manifests as bone fragility, craniosynostosis, ocular proptosis, hydrocephalus, and distinctive facial features. Only 2 types of mutation sites in the P4HB and CRTAP genes have been reported. A 14-month-old Chinese girl presented with prominent ocular proptosis, frontal bossing, craniosynostosis, plump anterior fontanel, growth retardation, osteopenia, and distinctive facial features that were strikingly similar to those in the original 2 cases. Whole-exome sequencing revealed a novel deletion variation in exons 5 to 8 of the P4HB gene, which was found to be heterozygous using fluorogenic quantitative-polymerase chain reaction. This de novo deletion mutation in exons 5 to 8 of the P4HB gene advances our understanding of CLCRP1, expands the mutation spectrum of P4HB, and diversifies the cases reported for this condition. Copyright © 2017 The Authors. Published by Wolters Kluwer Health, Inc. All rights reserved.

  19. Bismuth on copper (110): analysis of the c(2x2) and p(4x1) structures by surface x-ray diffraction

    DEFF Research Database (Denmark)

    Lottermoser, L.; Buslaps, T.; Johnson, R.L.

    1997-01-01

    Surface X-ray diffraction has been used to analyze the atomic structures of the Cu(110)-c(2 x 2)-Bi and Cu(110)-p(4 x 1)-Bi reconstructions with submonolayer coverages. A quasi-hexagonal c(2 x 2) adlayer structure is formed when half a monolayer of bismuth is deposited; the coverage corresponds...

  20. Changes in the distribution of lineage constellations of G2P[4] Rotavirus A strains detected in Japan over 32 years (1980-2011).

    Science.gov (United States)

    Doan, Yen Hai; Nakagomi, Toyoko; Agbemabiese, Chantal Ama; Nakagomi, Osamu

    2015-08-01

    Rotavirus A (RVA) is a leading cause of acute gastroenteritis in young children worldwide. Most human RVA strains are classified into three major genotype constellations: Wa-like, DS-1-like and AU-1-like. The evolution of G2P[4] strains possessing the DS-1-like genetic background was described in a few recent studies. However, the strains analyzed in these studies were almost exclusively the ones detected after 2000. In recognition of the scarcity of G2P[4] strains detected before 2000 for which whole genome information was available, this study was undertaken to characterize 19 Japanese G2P[4] strains detected between 1983 and 1990 (14 strains) and between 2001 and 2011 (5 strains), and to compare them with 131 G2P[4] strains from across the world. The Japanese strains along with the strains elsewhere in the world underwent stepwise changes from lineage I to IVa in 5 genes (the VP7, VP4, VP2, NSP1 and NSP5 genes) and from lineage I to V in 6 genes (the VP6, VP1, VP3, NSP2, NSP3 and NSP4 genes). Furthermore, G2P[4] strains detected after 2004 appeared to have undergone further intragenotype reassortment, resulting in the emergence of lineage V in the VP7 gene, and VI and VII in the VP3 and NSP4 genes. The time of the most recent common ancestor (tMRCA) for the emergent lineages VI and VII was estimated to be around the early 2000s. However, the year when the ancestor of the emergent lineages diverged from that of the rest of the lineages in the respective genes preceded the tMRCA 80-90 years. The origin of the emergent lineages is likely to be human RVA strains possessing genotypes other than G2P[4], and not RVA strains of an animal origin. In conclusion, stepwise changes in lineages imparted new genomic constellations to G2P[4] strains, which appears to have contributed to their successful spread across the globe, most notably since 2004. Copyright © 2015 Elsevier B.V. All rights reserved.

  1. Changing patterns of rotavirus strains circulating in Ireland: re-emergence of G2P[4] and identification of novel genotypes in Ireland.

    Science.gov (United States)

    Collins, P J; Mulherin, Emily; O'Shea, Helen; Cashman, Olivia; Lennon, Grainne; Pidgeon, Eugene; Coughlan, Suzie; Hall, William; Fanning, Séamus

    2015-05-01

    Worldwide, Group A Rotavirus (RVA) is recognized as the most common aetiological agent of acute diarrheal disease in children. One hundred and ninety seven positive faecal samples were obtained from patients between 2006 and 2008. Reverse transcriptase polymerase chain reaction (RT-PCR) was used to amplify the VP7 and VP4 gene segments of these samples, and G and P typing was carried out subsequently. The most common strain type was G1P[8], and the emergent global G9-type was identified in both years. RVA strain type G2P[4], previously reported in Ireland in 1999, was also detected. Genotypes G2 and G3 in combination with P[4] were detected in 2006-2007 only. There was also an emergence of strain types including G3P[4], G9P[4], G2P[4 + 8] and G2G4P[8] in this study. Molecular analysis of the VP7 genes revealed G1 strains circulating within lineage Ic as previously reported in Ireland. In addition, new sublineage within lineage I of G1 strains was also identified. Analysis of G4 strain NRVL-Hum-49 revealed similarity with other human G4 viruses in lineage Ib. G9 strain NRVL-Hum-74 clustered with a unique G9 strain, CIT-254, in lineage IIIc. This data supports the observations made that the profile of RVA strains in Ireland appears to be dynamic. This study demonstrates that the circulation of human rotavirus is changing continuously in Ireland, and continued surveillance of the circulating strains is needed to detect the appearance of new strains, or new variants which may lead to vaccine breakthrough. © 2015 Wiley Periodicals, Inc.

  2. Considerations on incoherency of boiling and voiding in lmfbr subassemblies during a loss-of-flow accident

    International Nuclear Information System (INIS)

    Nijsing, R.; Eifler, W.

    1978-01-01

    This paper deals with the transient thermohydraulic behaviour of liquid metal fast breeder subassemblies subjected of loss-of-flow. It shows that temperature incoherency effects in the subassembly give rise to a more gradual boiling- and voiding process than expected on the basis of a one-dimensional approach. Objectives of the paper are (a)to provide information on the multisubchannel code ''THARC'', (b) to present data on ''intrasubassembly'' incoherency effects, (c) to discuss aspects associated with code validation in out-of-pile bundle experiments. (author)

  3. Maintenance and repair of LMFBR steam generators. IV. Phenix steam generators Na H2O reaction incident

    International Nuclear Information System (INIS)

    Verriere, P.; Alanche, J.; Minguet, J.L.

    2002-01-01

    In 1982 and 1983, four leaks occurred on the steam generators of Phenix reactor, causing each time minor sodium-water reactions. Besides the short description of the steam generators, this paper describes in detail these incidents and subsequent repair procedures. The first leak occurred after 9 years of of operation when it was no longer expected. It provided experience to the personnel and represented a trial for the procedure. Apart from the check valve the equipment behaved well. Excellent behaviour of the hydrogen detection system is emphasised, meaning sensitivity and high reliability. Its limits are mentioned. They are concerned with response time of several tens of seconds inherent in the sampling system which could be a detrimental factor in the event of a higher leakage flow rate. The advantage of the modular steam generator design in respect to easy location of the faulty module is stressed. This enables rapid action for removing the module from service

  4. BLOW-3A. A theoretical model to describe transient two-phase flow conditions in LMFBR coolant channels

    International Nuclear Information System (INIS)

    Bottoni, M.; Struwe, D.

    1982-12-01

    The computer programme BLOW-3A describes sodium boiling phenomena in subassemblies of fast breeder reactors as well as in in-pile or out-of-pile experiments simulating different failure conditions. This report presents a complete documentation of the code from three main viewpoints: the theoretical foundations of the programme are first described with particular reference to the most recent developments; the structure of the programme is then explained in all details necessary for the user to get a rapid acquaintance with it; eventually several examples of the programme validation are discussed thus enabling the reader to acquire a full picture of the possible applications of the code and at the same time to know its validity range. (orig.) [de

  5. A synthesis of ten years' tests on scale models of LMFBR steam generators at the CGVS facility

    International Nuclear Information System (INIS)

    Fontaine, J.P.; Quinet, J.L.

    1982-01-01

    Electricite de France has built a high power sodium heated steam generator (SG) facility (CGVS), capable of reproducing all possible operating conditions, to study the behaviour of scale-models of industrial apparatuses. The main findings of the experiments were as follows: - heat exchange surfaces remained perfectly leak proof; - hydrogen detection in the sodium and argon constitute additional systems for monitoring the impermeability to leaks of a SG with a free sodium surface; - extrapolation of the findings to the SUPER PHENIX SG shows that water leaking at a rate of 100 mg/s would induce in ten minutes a 50% rise of the signal produced by the hydrogen monitoring device in the sodium; - acoustic method can detect leaks of the order of one g/s in a 45 MW SG sited in an industrial environment

  6. Prehistoric spatial patterning and subsistence studies: Archaeological investigations at Sample Unit U19arP4, Nevada Test Site, Nye County, Nevada

    International Nuclear Information System (INIS)

    Johnson, W.G.; DuBarton, A.; Edwards, S.; Drollinger, H.

    1992-01-01

    This report documents the methods and results of archaeological investigations at Sample Unit U19arP4 on Pahute Mesa at the Nevada Test Site (NTS). Eight sites were located there: four lithic artifact scatters (26NY1370, 26NY1372, 26NY3666 and 26NY3667), two temporary camps (26NY3665 and 26NY5418), one artifact locality (26NY5419), and one quarry (26NY3664). One of the lithic scatters, 26NY3667, incorporated a previously recorded rock ring, 26NY1371, that could not be relocated during subsequent investigations. Surface artifacts were collected from all but two of the sites, 26NY1370 and 26NY1372. The data retrieved from these investigations include over one thousand artifacts, such as projectile points, bifaces, debitage, groundstone, and pottery. The temporally diagnostic materials indicate periodic use of Sample Unit U19arP4 from the Middle Archaic to the Shoshonean period

  7. Critical roles of isoleucine-364 and adjacent residues in a hydrophobic gate control of phospholipid transport by the mammalian P4-ATPase ATP8A2

    DEFF Research Database (Denmark)

    Vestergaard, Anna L; Coleman, Jonathan A; Lemmin, Thomas

    2014-01-01

    the importance of amino acid residues in transmembrane segment M4 of mammalian P4-ATPase ATP8A2 by mutagenesis. In the related ion pumps Na+,K+-ATPase and Ca2+-ATPase, M4 moves during the enzyme cycle, carrying along the ion bound to a glutamate. In ATP8A2, the corresponding residue is an isoleucine, which......P4-ATPases (flippases) translocate specific phospholipids such as phosphatidylserine from the exoplasmic leaflet of the cell membrane to the cytosolic leaflet, upholding an essential membrane asymmetry. The mechanism of flipping this giant substrate has remained an enigma. We have investigated......, the phosphatidylserine head group passes near isoleucine-364 (I364) and that I364 is critical to the release of the transported lipid into the cytosolic leaflet. Another M4 residue, N359, is involved in recognition of the lipid substrate on the exoplasmic side. Our functional studies are supported by structural homology...

  8. Enzyme-linked immunosorbent serum assay specific for the 7S domain of Collagen Type IV (P4NP 7S)

    DEFF Research Database (Denmark)

    Leeming, Diana J; Nielsen, Mette J; Dai, Yueqin

    2012-01-01

    Aim:  The present study describes the ability of a newly developed N-terminal pro-peptides of type IV collagen 7S domain (P4NP 7S) competitive enzyme-linked immunosorbent assay (ELISA) for describing liver fibrosis. The assay applies a monoclonal antibody specific for a PIVNP 7S epitope 100...... were significantly elevated in rat with liver fibrosis as seen by histology (CCL4: 283% elevated in the highest quartile of total hepatic collagen compared with controls, P = 0.001; BDL: 183% elevated at week 4 compared with sham, P type IV collagen...... expression in BDL rats (r = 0.49, P serum assay specific for P4NP 7S was highly related to liver fibrosis...

  9. Reactor dosimetry integral reaction rate data in LMFBR Benchmark and standard neutron fields: status, accuracy and implications

    International Nuclear Information System (INIS)

    Fabry, A.; Ceulemans, H.; Vandeplas, P.; McElroy, W.N.; Lippincott, E.P.

    1977-01-01

    This paper provides conclusions that may be drawn regarding the consistency and accuracy of dosimetry cross-section files on the basis of integral reaction rate data measured in U.S. and European benchmark and standard neutron fields. In a discussion of the major experimental facilities CFRMF (Idaho Falls), BIGTEN (Los Alamos), ΣΣ (Mol, Bucharest), NISUS (London), TAPIRO (Roma), FISSION SPECTRA (NBS, Mol, PTB), attention is paid to quantifying the sensitivity of computed integral data relative to the presently evaluated accuracy of the various neutron spectral distributions. The status of available integral data is reviewed and the assigned uncertainties are appraised, including experience gained by interlaboratory comparisons. For all reactions studied and for the various neutron fields, the measured integral data are compared to the ones computed from the ENDF/B-IV and the SAND-II dosimetry cross-section libraries as well as to some other differential data in relevant cases. This comparison, together with the proposed sensitivity and accuracy assessments, is used, whenever possible, to establish how well the best cross-sections evaluated on the basis of differential measurements (category I dosimetry reactions) are reliable in terms of integral reaction rates prediction and, for those reactions for which discrepancies are indicated, in which energy range it is presumed that additional differential measurements might help. For the other reactions (category II), the inconsistencies and trends are examined. The need for further integral measurements and interlaboratory comparisons is also considered

  10. Synthesis, structure, and properties of Cs(4)Th(4)P(4)Se(26): a quaternary thorium selenophosphate containing the (P(2)Se(9))(6-) anion.

    Science.gov (United States)

    Briggs Piccoli, P M; Abney, K D; Schoonover, J D; Dorhout, P K

    2001-09-10

    Orange crystals of Cs(4)Th(4)P(4)Se(26) were grown from the reaction of (232)Th and P in a Cs(2)Se(3)/Se molten salt flux at 750 degrees C. Cs(4)Th(4)P(4)Se(26) crystallizes in the orthorhombic space group Pbca with the unit cell parameters: a = 12.0130(6), b = 14.5747(7), c = 27.134(1) A; Z = 8. The compound exhibits a three-dimensional structure, consisting of dimeric [Th(2)Se(13)] polyhedral units. The two crystallographically independent, nine-coordinate, bicapped trigonal prismatic thorium atoms share a triangular face to form the dimer, and each dimer edge-shares two selenium atoms with two other dimers to form kinked chains along the [010] direction. While this structure shares features of the previously reported Rb(4)U(4)P(4)Se(26), including phosphorus in the 5+ oxidation state, careful inspection of the structure reveals that the selenophosphate anion that knits the structure together in three directions in both compounds is a unique (P(2)Se(9))(6-) anion. The formula may be described best as [Cs(2)Th(2)(P(2)Se(9))(Se(2))(2)](2). The (P(2)Se(9))(6-) anion features a nearly linear Se-Se-Se backbone with an angle of 171 degrees and Se-Se distances that are approximately 0.2-0.3 A longer than the typical single Se-Se bond. Magnetic studies confirm that this phase contains Th(IV). Raman data for this compound is reported, and structural comparisons will be drawn to its uranium analogue, Rb(4)U(4)P(4)Se(26).

  11. Prenatal diagnosis and molecular cytogenetic characterization of a de novo proximal interstitial deletion of chromosome 4p (4p15.2→p14).

    Science.gov (United States)

    Chen, Chih-Ping; Lee, Meng-Ju; Chern, Schu-Rern; Wu, Peih-Shan; Su, Jun-Wei; Chen, Yu-Ting; Lee, Meng-Shan; Wang, Wayseen

    2013-10-25

    We present prenatal diagnosis of de novo proximal interstitial deletion of chromosome 4p (4p15.2→p14) and molecular cytogenetic characterization of the deletion using uncultured amniocytes. We review the phenotypic abnormalities of previously reported patients with similar proximal interstitial 4p deletions, and we discuss the functions of the genes of RBPJ, CCKAR, STIM2, PCDH7 and ARAP2 that are deleted within this region. © 2013.

  12. Regeneration of Cystic Bone Cavities and Bone Defects With Bioactive Glass S53P4 in the Upper and Lower Jaws.

    Science.gov (United States)

    Stoor, Patricia; Apajalahti, Satu; Kontio, Risto

    2017-07-01

    Cysts and tumors are common lesions in the jaws. To be able to retain a good volume of the alveolar ridge during healing as well as strengthening the angle and body of the mandible and provide an instant improved support for adjacent teeth, reliable long-term bone regeneration is needed. The purpose of this prospective study was to promote bone regeneration by filling bony defects in the upper or lower jaw with granules of the bioactive glass S53P4 (BAG), which have osteostimulative and antimicrobial properties.The authors treated 20 patients (21 defects) surgically; benign tumors, cysts, or infection related to impacted teeth in the maxilla or mandible. The tumor or cyst was removed or enucleated and thorough cleaning of the infected area was performed. The bone cavity was filled with granules of the BAG S53P4 despite signs of chronic infection in the area at the time of surgery. The patients were followed up for an average of 34 months clinically and with cone beam computerized tomography for 28 months. In 20 defects the final outcome was successful. Despite infection at the time of surgery in 65% of the patients, no material associated infection was seen during the follow-up. The BAG S53P4 granules were radiologically remodeled into bone after 2 years follow-up. The use of granules of the BAG S53P4 in the treatment of large bone defects provides infection-free reliable bone regeneration despite chronic infection at the time of surgery, which improves the prognosis of adjacent teeth.

  13. P4 Stump Approach for Intraoperative Portal Vein Stenting in Pediatric Living Donor Liver Transplantation: An Innovative Technique for a Challenging Problem.

    Science.gov (United States)

    Chen, Chao-Long; Cheng, Yu-Fan; Huang, Viola; Lin, Ting-Lung; Chan, Yi-Chia; Ou, Hsin-You; Yong, Chee-Chien; Wang, Shih-Ho; Lin, Chih-Che

    2018-03-01

    The aim of this study was to evaluate the utility of the P4 stump stenting approach for treating portal vein (PV) complications in pediatric living donor liver transplantation (LDLT). PV complications cause significant morbidity and mortality in pediatric LDLT. Biliary atresia in the backdrop of pathological PV hypoplasia and sclerosis heightens the complexity of PV reconstruction. The authors developed a novel approach for intraoperative PV stenting via the graft segment 4 PV stump (P4 stump) to address this challenge. From April 2009 to December 2016, 15 pediatric LDLT recipients (mean age 10.3 ± 5.0 months, mean graft-recipient weight ratio 3.70%) underwent intraoperative stenting for suboptimal PV flow (approach, the incidence of variceal bleeding as a late complication decreased from 7% to zero. The P4 stump stenting approach affords procedural convenience, ease of manipulation, and consistent results with the potential for excellent long-term patency in children despite continued growth. This technique obviates the need for more demanding post-transplant stenting, and may become a substitute for complicated revision surgery, portosystemic shunting, or retransplantation.

  14. GE post-test analysis of SLSF experiment W-1 through LOPI-4

    International Nuclear Information System (INIS)

    Gregoire, K.E.; Atcheson, D.B.; Knight, D.D.

    1981-07-01

    SLSF experiment W-1 was designed to investigate fuel pin-to-coolant heat transfer during various LMFBR flow-coastdown events in the burnup interval from 0.0 atom percent to 0.5 atom percent. In the study reported here, data from in-fuel thermocouples and coolant (wire-wrap) thermocouples were evaluated during steady-state and transient operation from the beginning of the experiment through LOPI-4 (Loss-of-Piping-Integrity Transient Number 4). The objective of the data evaluation was to determine how maximum coolant temperatures during successive LOPI transients were affected by burnup. A second objective was to identify the mechanisms responsible for this burnup effect

  15. Results of the GAP-4 experiment on molten-fuel drainage through intersubassembly gap geometry

    International Nuclear Information System (INIS)

    Spencer, B.W.; Vetter, D.; Wesel, R.; Sienicki, J.J.

    1983-01-01

    One of the key issues in assessment of the meltout phase of a hypothetical core disruptive accident in the LMFBR system involves the timing and paths for dispersal of molten fuel from the disrupted core. A program of experiments is underway at Argonne National Laboratory to investigate molten fuel penetration through these postulated escape paths. The purpose of the GAP-4 test was to examine the penetration distances of molten fuel flowing through the flat, narrow channels representing the intersubassembly gap geometry. In the experiment design, the gap geometry was selected to be two-dimensional on the basis that the gap volume in a reactor design would be interconnected and continuous. The molten fuel used in these tests was a mixture of UO 2 (81%) and molybdenum (19%) which was generated by an exothermic thermite reaction at a temperature of approx. 3470 K

  16. Repeated circulation over 6 years of intergenogroup mono-reassortant G2P[4] rotavirus strains with genotype N1 of the NSP2 gene.

    Science.gov (United States)

    Doan, Yen Hai; Nakagomi, Toyoko; Nakagomi, Osamu

    2012-08-01

    Human rotavirus A, a major cause of acute diarrhoea in infants and young children worldwide, contains the genome of 11 segments of double-stranded RNA, which is grouped into three major genotype constellations: the Wa genogroup (G1-P[8]-I1-R1-C1-M1-A1-N1-T1-E1-H1), the DS-1 genogroup (G2-P[4]-I2-R2-C2-M2-A2-N2-T2-E2-H2), and the AU-1 genogroup (G3-P[9]-I3-R3-C3-M3-A3-N3-T3-E3-H3). Recently, a G2P[4] strain detected in Kenya in 1982 was reported to be a nonstructural protein 2 (NSP2) gene mono-reassortant between the Wa and DS-1 genogroups. While NSP2 induces heterotypic antibody responses in children, thereby being the likely target of immune selective pressure, it was not known how frequently these NSP2 mono-reassortants circulated among children. In a previous 10 year epidemiological study, out of 100 G2P[4] rotavirus specimens that were typed into 22 distinct electropherotypes (i.e., strains), RNA-RNA hybridization identified that 12 strains were mono-reassortants involving either the NSP2 or the NSP3 gene. The aim of this study was therefore to determine the nucleotide sequences of all 11 genes of the representative mono-reassortant strain (AU605) and the sequences of the reassorted genes of the other mono-reassortant strains. The genome constellation of AU605 was G2-P[4]-I2-R2-C2-M2-A2-N1-T2-E2-H2, indicating that it was a mono-reassortant strain carrying a Wa-like NSP2 genotype on the DS-1 genogroup background. The reassorted gene of the other 11 strains also had the genotype N1 in the NSP2 gene. Given that electrophoretically-identical rotaviruses represent a single strain, the 12 NSP2 mono-reassortants detected in six rotavirus seasons accounted for 36% (36 of 100) of G2P[4] rotavirus specimens in the 10 year collection. The circulation of NSP2 mono-reassortant strains was observed in epidemic seasons when the G2P[4] genotype was not dominant. Taken together with their repeated occurrence at higher-than-expected frequencies, the identification of NSP2 mono

  17. LMFBR design and its evolution. (2) Core design of LMFBR

    International Nuclear Information System (INIS)

    Uto, Nariaki; Mizuno, Tomoyasu

    2003-01-01

    Sodium-cooled core design studies are performed. MOX fuel core with axial blanket partial elimination subassembly due to safety consideration is studied. This type of core with high internal conversion ratio possesses capability of achieving 26 months of operation cycle length and 100 GWd/t of burnup averaged over core and blanket, which are superior characteristics in view of reducing cost of power generation. Metal fuel core is also studied, and its higher breeding capability reveals a potential of better core performance such as longer operation cycle length for the same level of electricity generation, though core outlet temperature is limited to lower level due to steel cladding-metal fuel compatibility concerns. Another metal fuel core concept using single Pu enrichment and two radial regions with individual fuel pin diameters achieves 550degC of core outlet temperature identical to that of MOX fuel core, keeping operation cycle length comparable with that of MOX fuel core. This series of study results show that sodium-cooled MOX and metal fuel cores have a high flexibility in satisfying various needs including fuel cycle cost and breeding capability, depending on the stage of introducing commercialized fast reactor cycle system. (author)

  18. An innovative pay-for-performance (P4P) strategy for improving malaria management in rural Kenya: protocol for a cluster randomized controlled trial.

    Science.gov (United States)

    Menya, Diana; Logedi, John; Manji, Imran; Armstrong, Janice; Neelon, Brian; O'Meara, Wendy Prudhomme

    2013-05-08

    In high-resource settings, 'pay-for-performance' (P4P) programs have generated interest as a potential mechanism to improve health service delivery and accountability. However, there has been little or no experimental evidence to guide the development or assess the effectiveness of P4P incentive programs in developing countries. In the developing world, P4P programs are likely to rely, at least initially, on external funding from donors. Under these circumstances, the sustainability of such programs is in doubt and needs assessment. We describe a cluster-randomized controlled trial underway in 18 health centers in western Kenya that is testing an innovative incentive strategy to improve management of an epidemiologically and economically important problem--diagnosis and treatment of malaria. The incentive scheme in this trial promotes adherence to Ministry of Health guidelines for laboratory confirmation of malaria before treatment, a priority area for the Ministry of Health. There are three important innovations that are unique to this study among those from other resource-constrained settings: the behavior being incentivized is quality of care rather than volume of service delivery; the incentives are applied at the facility-level rather than the individual level, thus benefiting facility infrastructure and performance overall; and the incentives are designed to be budget-neutral if effective. Linking appropriate case management for malaria to financial incentives has the potential to improve patient care and reduce wastage of expensive antimalarials. In our study facilities, on average only 25% of reported malaria cases were confirmed by laboratory diagnosis prior to the intervention, and the total treatment courses of antimalarials dispensed did not correspond to the number of cases reported. This study will demonstrate whether facility rather than individual incentives are compelling enough to improve case management, and whether these incentives lead to

  19. Analysis of Amino Acid Residues of Potential Importance for Phosphati-dylserine Specificity of P4-type ATPase ATP8A2

    DEFF Research Database (Denmark)

    Mogensen, Louise; Vestergaard, Anna Lindeløv; Mikkelsen, Stine

    The asymmetric structure of the plasma membrane is maintained through internalization of phos-pholipids by the family of P4-ATPases by a poorly characterized mechanism. Studies in yeast point towards a non-classical pathway involving important residues of a two-gate mechanism [1]. Glycine-230...... together with their maximal velocity have been analyzed by an ATPase activity assay and compared with those of the wild type ATP8A2 protein. Also, partial reaction steps of the catalytic cycle of these ATP8A2 mutants were studied by phos-phorylation assays. Our results indicate both similarities...

  20. A theoretical survey of 4s-4p and 4p-4d transitions in nickel-like ions through Sn XXIII

    International Nuclear Information System (INIS)

    Wyart, J.F.

    1987-01-01

    The predictions of 4s-4p and 4p-4d transitions derived from Slater-Condon type calculations of 3d 9 4s, -4p and -4d configurations in the sequence Zn III-Se VII have been recently confirmed experimentally through Mo XV. These new data are used here to refine the predictions in the sequence Mo XV-Sn XXIII. The radial parameters involved in the three configurations are determined in generalized least-squares fits using all known levels in the sequence. (orig.)

  1. TNO contribution to LMFBR development

    NARCIS (Netherlands)

    1973-01-01

    As TNO started work on the use of sodium as a coolant more than ten years ago, and as our latest status report was presented some five years ago, it seemed appropriate to show you once more the status of our work.

  2. Dynamic simulation of LMFBR systems

    International Nuclear Information System (INIS)

    Agrawal, A.K.; Khatib-Rahbar, M.

    1980-01-01

    This review article focuses on the dynamic analysis of liquid-metal-cooled fast breeder reactor systems in the context of protected transients. Following a brief discussion on various design and simulation approaches, a critical review of various models for in-reactor components, intermediate heat exchangers, heat transport systems and the steam generating system is presented. A brief discussion on choice of fuels as well as core and blanket system designs is also included. Numerical considerations for obtaining system-wide steady-state and transient solutions are discussed, and examples of various system transients are presented. Another area of major interest is verification of phenomenological models. Various steps involved in the code and model verification are briefly outlined. The review concludes by posing some further areas of interest in fast reactor dynamics and safety. (author)

  3. LMFBR Ultra Long Life Cores

    International Nuclear Information System (INIS)

    Schmidt, J.E.; Doncals, R.A.; Porter, C.A.; Gundy, L.M.

    1986-01-01

    The Ultra Long Life Core is an attractive and innovative design approach with several extremely beneficial attributes. Long Life cores are applicable to the full range of LMR plant sizes resulting in lifetimes up to 30 years. Core life is somewhat limited for smaller plant sizes, however significant benefits of this approach still exist for all plant sizes. The union of long life cores and the complementary inherent safety technology offer a means of utilizing the well-proven oxide fuel in a system with unsurpassed safety capability. A further benefit is that the uranium fuel cycle can be used in long life cores, especially for initial LMR plant deployment, thereby eliminating the need for reprocessing prior to starting LMR plant construction in the U.S. Finally the long life core significantly reduces power costs. With inherent safety capability designed into an LMR and with the ULLC fuel cycle, power costs competitive with light water plants are achievable while offering improved operational flexibility derived through extending refueling intervals

  4. NadN and e (P4) Are Essential for Utilization of NAD and Nicotinamide Mononucleotide but Not Nicotinamide Riboside in Haemophilus influenzae

    Science.gov (United States)

    Kemmer, Gabriele; Reilly, Thomas J.; Schmidt-Brauns, Joachim; Zlotnik, Gary W.; Green, Bruce A.; Fiske, Michael J.; Herbert, Mark; Kraiß, Anita; Schlör, Stefan; Smith, Arnold; Reidl, Joachim

    2001-01-01

    Haemophilus influenzae has an absolute requirement for NAD (factor V) because it lacks almost all the biosynthetic enzymes necessary for the de novo synthesis of that cofactor. Factor V can be provided as either nicotinamide adenosine dinucleotide (NAD), nicotinamide mononucleotide (NMN), or nicotinamide riboside (NR) in vitro, but little is known about the source or the mechanism of uptake of these substrates in vivo. As shown by us earlier, at least two gene products are involved in the uptake of NAD, the outer membrane lipoprotein e (P4), which has phosphatase activity and is encoded by hel, and a periplasmic NAD nucleotidase, encoded by nadN. It has also been observed that the latter gene product is essential for H. influenzae growth on media supplemented with NAD. In this report, we describe the functions and substrates of these two proteins as they act together in an NAD utilization pathway. Data are provided which indicate that NadN harbors not only NAD pyrophosphatase but also NMN 5′-nucleotidase activity. The e (P4) protein is also shown to have NMN 5′-nucleotidase activity, recognizing NMN as a substrate and releasing NR as its product. Insertion mutants of nadN or deletion and site-directed mutants of hel had attenuated growth and a reduced uptake phenotype when NMN served as substrate. A hel and nadN double mutant was only able to grow in the presence of NR, whereas no uptake of NMN was observed. PMID:11395461

  5. Synthesis of Mo–Fe3O4@SiO2@P4VP core–shell–shell structured magnetic microspheres for alkene epoxidation reactions

    International Nuclear Information System (INIS)

    Huang, Xiubing; Guo, Wanchun; Wang, Ge; Yang, Mu; Wang, Qian; Zhang, Xinxin; Feng, Yanhui; Shi, Zhan; Li, Chunguang

    2012-01-01

    Molybdenum complexes immobilized on core–shell–shell structured Fe 3 O 4 @SiO 2 @poly(4-vinylpyridine) microspheres have been successfully fabricated by grafting [3-(methacryloyloxy)propyl]trimethoxysilane on Fe 3 O 4 @SiO 2 followed by seeded emulsion polymerization of 4-vinylpyridine monomers. The synthesized samples were characterized by X-ray diffraction (XRD), transmission electron microscopy (TEM), field-emission scanning electron microscopy (FESEM), x-ray photoelectron spectroscopy (XPS), Fourier-transform infrared spectra (FT-IR) and magnetometer. Their catalytic property was investigated by epoxidation of alkenes, using environmentally friendly H 2 O 2 and ethanol as oxidant and solvent, respectively. The results show that Mo–Fe 3 O 4 @SiO 2 @P4VP catalyst possesses high conversion (99.0%) and selectivity (99.0%) in the epoxidation of cis-cyclooctene at 60 °C for 24 h, and the catalyst can be recovered using a magnet and still shows high conversion (95.0%) and selectivity (99.0%) after being recycled three times. -- Highlights: ► Core–shell–shell structured Mo–Fe 3 O 4 @SiO 2 @P4VP microspheres were fabricated. ► The catalyst shows high activity in the epoxidation of alkenes. ► Environmentally friendly H 2 O 2 and ethanol are used as oxidant and solvent. ► The catalyst can be quickly magnetically recovered and maintains high activity.

  6. NadN and e (P4) are essential for utilization of NAD and nicotinamide mononucleotide but not nicotinamide riboside in Haemophilus influenzae.

    Science.gov (United States)

    Kemmer, G; Reilly, T J; Schmidt-Brauns, J; Zlotnik, G W; Green, B A; Fiske, M J; Herbert, M; Kraiss, A; Schlör, S; Smith, A; Reidl, J

    2001-07-01

    Haemophilus influenzae has an absolute requirement for NAD (factor V) because it lacks almost all the biosynthetic enzymes necessary for the de novo synthesis of that cofactor. Factor V can be provided as either nicotinamide adenosine dinucleotide (NAD), nicotinamide mononucleotide (NMN), or nicotinamide riboside (NR) in vitro, but little is known about the source or the mechanism of uptake of these substrates in vivo. As shown by us earlier, at least two gene products are involved in the uptake of NAD, the outer membrane lipoprotein e (P4), which has phosphatase activity and is encoded by hel, and a periplasmic NAD nucleotidase, encoded by nadN. It has also been observed that the latter gene product is essential for H. influenzae growth on media supplemented with NAD. In this report, we describe the functions and substrates of these two proteins as they act together in an NAD utilization pathway. Data are provided which indicate that NadN harbors not only NAD pyrophosphatase but also NMN 5'-nucleotidase activity. The e (P4) protein is also shown to have NMN 5'-nucleotidase activity, recognizing NMN as a substrate and releasing NR as its product. Insertion mutants of nadN or deletion and site-directed mutants of hel had attenuated growth and a reduced uptake phenotype when NMN served as substrate. A hel and nadN double mutant was only able to grow in the presence of NR, whereas no uptake of NMN was observed.

  7. Masses and sigma terms of doubly charmed baryons up to O (p4) in manifestly Lorentz-invariant baryon chiral perturbation theory

    Science.gov (United States)

    Yao, De-Liang

    2018-02-01

    We calculate the masses and sigma terms of the doubly charmed baryons up to next-to-next-to-next-to-leading order [i.e., O (p4) ] in a covariant baryon chiral perturbation theory by using the extended-on-mass-shell renormalization scheme. Their expressions both in infinite and finite volumes are provided for chiral extrapolation in lattice QCD. As a first application, our chiral results of the masses are confronted with the existing lattice QCD data in the presence of finite-volume corrections. Up to O (p3) , all relevant low-energy constants can be well determined. As a consequence, we obtain the physical values for the masses of Ξc c and Ωc c baryons by extrapolating to the physical limit. Our determination of the Ξc c mass is consistent with the recent experimental value by LHCb Collaboration, however, larger than the one by SELEX Collaboration. In addition, we predict the pion-baryon and strangeness-baryon sigma terms, as well as the mass splitting between the Ξc c and Ωc c states. Their quark mass dependences are also discussed. The numerical procedure can be applied to the chiral results of O (p4) order, where more unknown constants are involved, when more data are available for unphysical pion masses.

  8. Combined Chlorophyll Fluorescence and Transcriptomic Analysis Identifies the P3/P4 Transition as a Key Stage in Rice Leaf Photosynthetic Development.

    Science.gov (United States)

    van Campen, Julia C; Yaapar, Muhammad N; Narawatthana, Supatthra; Lehmeier, Christoph; Wanchana, Samart; Thakur, Vivek; Chater, Caspar; Kelly, Steve; Rolfe, Stephen A; Quick, W Paul; Fleming, Andrew J

    2016-03-01

    Leaves are derived from heterotrophic meristem tissue that, at some point, must make the transition to autotrophy via the initiation of photosynthesis. However, the timing and spatial coordination of the molecular and cellular processes underpinning this switch are poorly characterized. Here, we report on the identification of a specific stage in rice (Oryza sativa) leaf development (P3/P4 transition) when photosynthetic competence is first established. Using a combined physiological and molecular approach, we show that elements of stomatal and vascular differentiation are coordinated with the onset of measurable light absorption for photosynthesis. Moreover, by exploring the response of the system to environmental perturbation, we show that the earliest stages of rice leaf development have significant plasticity with respect to elements of cellular differentiation of relevance for mature leaf photosynthetic performance. Finally, by performing an RNA sequencing analysis targeted at the early stages of rice leaf development, we uncover a palette of genes whose expression likely underpins the acquisition of photosynthetic capability. Our results identify the P3/P4 transition as a highly dynamic stage in rice leaf development when several processes for the initiation of photosynthetic competence are coordinated. As well as identifying gene targets for future manipulation of rice leaf structure/function, our data highlight a developmental window during which such manipulations are likely to be most effective. © 2016 American Society of Plant Biologists. All Rights Reserved.

  9. Quadrupole and monopole generalized oscillator strength for 2p-3p, 2p-4p transition of neon atomic in the velocity formulation

    International Nuclear Information System (INIS)

    Gomis, L; Diedhiou, I; Tall, M S; Diallo, S; Diatta, C S; Niassy, B

    2007-01-01

    The quadrupole and monopole generalized oscillator strengths (GOS) as a function of momentum transfer are calculated for the 2p-3p and 2p-4p transitions of the neon atom using the analytical Hartree-Fock (HF) wavefunctions for the ground-state and the wavefunctions for the excited states which are obtained numerically from the modified HF Slater equation. Calculations are carried out by using the HF method and random phase approximation with exchange in the velocity formulation. The positions and the number of the extrema in the GOS have received particular attention in the evaluation. Our calculated monopole GOS of 2p-3p transition in velocity form reveals one maximum located between the experimental and theoretical results of other authors. The disagreement between our first maximum of the quadrupole GOS 2p-3p transition with the experimental and other theoretical ones is unimportant. The extrema of the monopole and quadrupole GOS of 2p-4p transition are given in this paper. The results of velocity form study also show that the electron correlation effects are important around the maxima and are found to influence the positions of the extrema insignificantly

  10. Dichloro-Cycloazatriphosphane: The Missing Link between N2P2and P4Ring Systems in the Systematic Development of NP Chemistry.

    Science.gov (United States)

    Bresien, Jonas; Hinz, Alexander; Schulz, Axel; Suhrbier, Tim; Thomas, Max; Villinger, Alexander

    2017-10-20

    A dichloro-cycloazatriphosphane that incorporates a cyclic NP 3 backbone could be synthesized using knowledge gained from the chemistry of N 2 P 2 and P 4 ring systems. It fills the gap between the congeneric compounds [ClP(μ-NR)] 2 and [ClP(μ-PR)] 2 (R=sterically demanding substituent), and thus contributes to the systematic development of nitrogen-phosphorus chemistry in general. The title compound was studied with respect to its formation via a labile aminodiphosphene, which readily underwent different rearrangement reactions depending on the solvent. All compounds were fully characterized by experimental and computational methods. © 2017 Wiley-VCH Verlag GmbH & Co. KGaA, Weinheim.

  11. C-terminus of the P4-ATPase ATP8A2 functions in protein folding and regulation of phospholipid flippase activity.

    Science.gov (United States)

    Chalat, Madhavan; Moleschi, Kody; Molday, Robert S

    2017-02-01

    ATP8A2 is a P4-ATPase that flips phosphatidylserine and phosphatidylethanolamine across cell membranes. This generates membrane phospholipid asymmetry, a property important in many cellular processes, including vesicle trafficking. ATP8A2 deficiency causes severe neurodegenerative diseases. We investigated the role of the C-terminus of ATP8A2 in its expression, subcellular localization, interaction with its subunit CDC50A, and function as a phosphatidylserine flippase. C-terminal deletion mutants exhibited a reduced tendency to solubilize in mild detergent and exit the endoplasmic reticulum. The solubilized protein, however, assembled with CDC50A and displayed phosphatidylserine flippase activity. Deletion of the C-terminal 33 residues resulted in reduced phosphatidylserine-dependent ATPase activity, phosphatidylserine flippase activity, and neurite extension in PC12 cells. These reduced activities were reversed with 60- and 80-residue C-terminal deletions. Unlike the yeast P4-ATPase Drs2, ATP8A2 is not regulated by phosphoinositides but undergoes phosphorylation on the serine residue within a CaMKII target motif. We propose a model in which the C-terminus of ATP8A2 consists of an autoinhibitor domain upstream of the C-terminal 33 residues and an anti-autoinhibitor domain at the extreme C-terminus. The latter blocks the inhibitory activity of the autoinhibitor domain. We conclude that the C-terminus plays an important role in the efficient folding and regulation of ATP8A2. © 2017 Chalat et al. This article is distributed by The American Society for Cell Biology under license from the author(s). Two months after publication it is available to the public under an Attribution–Noncommercial–Share Alike 3.0 Unported Creative Commons License (http://creativecommons.org/licenses/by-nc-sa/3.0).

  12. Catalytic Silylation of N2and Synthesis of NH3and N2H4by Net Hydrogen Atom Transfer Reactions Using a Chromium P4Macrocycle.

    Science.gov (United States)

    Kendall, Alexander J; Johnson, Samantha I; Bullock, R Morris; Mock, Michael T

    2018-02-21

    We report the first discrete molecular Cr-based catalysts for the reduction of N 2 . This study is focused on the reactivity of the Cr-N 2 complex, trans-[Cr(N 2 ) 2 (P Ph 4 N Bn 4 )] (P 4 Cr(N 2 ) 2 ), bearing a 16-membered tetraphosphine macrocycle. The architecture of the [16]-P Ph 4 N Bn 4 ligand is critical to preserve the structural integrity of the catalyst. P 4 Cr(N 2 ) 2 was found to mediate the reduction of N 2 at room temperature and 1 atm pressure by three complementary reaction pathways: (1) Cr-catalyzed reduction of N 2 to N(SiMe 3 ) 3 by Na and Me 3 SiCl, affording up to 34 equiv N(SiMe 3 ) 3 ; (2) stoichiometric reduction of N 2 by protons and electrons (for example, the reaction of cobaltocene and collidinium triflate at room temperature afforded 1.9 equiv of NH 3 , or at -78 °C afforded a mixture of NH 3 and N 2 H 4 ); and (3) the first example of NH 3 formation from the reaction of a terminally bound N 2 ligand with a traditional H atom source, TEMPOH (2,2,6,6-tetramethylpiperidine-1-ol). We found that trans-[Cr( 15 N 2 ) 2 (P Ph 4 N Bn 4 )] reacts with excess TEMPOH to afford 1.4 equiv of 15 NH 3 . Isotopic labeling studies using TEMPOD afforded ND 3 as the product of N 2 reduction, confirming that the H atoms are provided by TEMPOH.

  13. Critical roles of isoleucine-364 and adjacent residues in a hydrophobic gate control of phospholipid transport by the mammalian P4-ATPase ATP8A2.

    Science.gov (United States)

    Vestergaard, Anna L; Coleman, Jonathan A; Lemmin, Thomas; Mikkelsen, Stine A; Molday, Laurie L; Vilsen, Bente; Molday, Robert S; Dal Peraro, Matteo; Andersen, Jens Peter

    2014-04-08

    P4-ATPases (flippases) translocate specific phospholipids such as phosphatidylserine from the exoplasmic leaflet of the cell membrane to the cytosolic leaflet, upholding an essential membrane asymmetry. The mechanism of flipping this giant substrate has remained an enigma. We have investigated the importance of amino acid residues in transmembrane segment M4 of mammalian P4-ATPase ATP8A2 by mutagenesis. In the related ion pumps Na(+),K(+)-ATPase and Ca(2+)-ATPase, M4 moves during the enzyme cycle, carrying along the ion bound to a glutamate. In ATP8A2, the corresponding residue is an isoleucine, which recently was found mutated in patients with cerebellar ataxia, mental retardation, and dysequilibrium syndrome. Our analyses of the lipid substrate concentration dependence of the overall and partial reactions of the enzyme cycle in mutants indicate that, during the transport across the membrane, the phosphatidylserine head group passes near isoleucine-364 (I364) and that I364 is critical to the release of the transported lipid into the cytosolic leaflet. Another M4 residue, N359, is involved in recognition of the lipid substrate on the exoplasmic side. Our functional studies are supported by structural homology modeling and molecular dynamics simulations, suggesting that I364 and adjacent hydrophobic residues function as a hydrophobic gate that separates the entry and exit sites of the lipid and directs sequential formation and annihilation of water-filled cavities, thereby enabling transport of the hydrophilic phospholipid head group in a groove outlined by the transmembrane segments M1, M2, M4, and M6, with the hydrocarbon chains following passively, still in the membrane lipid phase.

  14. Kinetic and thermodynamic framework for P4-P6 RNA reveals tertiary motif modularity and modulation of the folding preferred pathway

    Science.gov (United States)

    Bisaria, Namita; Greenfeld, Max; Limouse, Charles; Pavlichin, Dmitri S.; Mabuchi, Hideo; Herschlag, Daniel

    2016-01-01

    The past decade has seen a wealth of 3D structural information about complex structured RNAs and identification of functional intermediates. Nevertheless, developing a complete and predictive understanding of the folding and function of these RNAs in biology will require connection of individual rate and equilibrium constants to structural changes that occur in individual folding steps and further relating these steps to the properties and behavior of isolated, simplified systems. To accomplish these goals we used the considerable structural knowledge of the folded, unfolded, and intermediate states of P4-P6 RNA. We enumerated structural states and possible folding transitions and determined rate and equilibrium constants for the transitions between these states using single-molecule FRET with a series of mutant P4-P6 variants. Comparisons with simplified constructs containing an isolated tertiary contact suggest that a given tertiary interaction has a stereotyped rate for breaking that may help identify structural transitions within complex RNAs and simplify the prediction of folding kinetics and thermodynamics for structured RNAs from their parts. The preferred folding pathway involves initial formation of the proximal tertiary contact. However, this preference was only ∼10 fold and could be reversed by a single point mutation, indicating that a model akin to a protein-folding contact order model will not suffice to describe RNA folding. Instead, our results suggest a strong analogy with a modified RNA diffusion-collision model in which tertiary elements within preformed secondary structures collide, with the success of these collisions dependent on whether the tertiary elements are in their rare binding-competent conformations. PMID:27493222

  15. Using pay for performance incentives (P4P) to improve management of suspected malaria fevers in rural Kenya: a cluster randomized controlled trial.

    Science.gov (United States)

    Menya, Diana; Platt, Alyssa; Manji, Imran; Sang, Edna; Wafula, Rebeccah; Ren, Jing; Cheruiyot, Olympia; Armstrong, Janice; Neelon, Brian; O'Meara, Wendy Prudhomme

    2015-10-16

    Inappropriate treatment of non-malaria fevers with artemisinin-based combination therapies (ACTs) is a growing concern, particularly in light of emerging artemisinin resistance, but it is a behavior that has proven difficult to change. Pay for performance (P4P) programs have generated interest as a mechanism to improve health service delivery and accountability in resource-constrained health systems. However, there has been little experimental evidence to establish the effectiveness of P4P in developing countries. We tested a P4P strategy that emphasized parasitological diagnosis and appropriate treatment of suspected malaria, in particular reduction of unnecessary consumption of ACTs. A random sample of 18 health centers was selected and received a refresher workshop on malaria case management. Pre-intervention baseline data was collected from August to September 2012. Facilities were subsequently randomized to either the comparison (n = 9) or intervention arm (n = 9). Between October 2012 and November 2013, facilities in the intervention arm received quarterly incentive payments based on seven performance indicators. Incentives were for use by facilities rather than as payments to individual providers. All non-pregnant patients older than 1 year of age who presented to a participating facility and received either a malaria test or artemether-lumefantrine (AL) were eligible to be included in the analysis. Our primary outcome was prescription of AL to patients with a negative malaria diagnostic test (n = 11,953). Our secondary outcomes were prescription of AL to patients with laboratory-confirmed malaria (n = 2,993) and prescription of AL to patients without a malaria diagnostic test (analyzed at the cluster level, n = 178 facility-months). In the final quarter of the intervention period, the proportion of malaria-negative patients in the intervention arm who received AL was lower than in the comparison arm (7.3% versus 10.9%). The improvement

  16. Millisecond-Period Meltdown Experiments on Prompt - Burst Effects and Molten-Tin-Water Dropping Experiments

    International Nuclear Information System (INIS)

    Wright, R.W.; Coats, R.L.; Schmidt, T.R.; Arakeri, V.H.

    1976-01-01

    The U.S. Nuclear Regulatory Commission has initiated a program of confirmatory research for the safety assessment of LMFBR plants. In the sodium-fuel interactions area, this research includes a series of real-time in-pile experiments on the pressure and work potential of prompt-burst excursions as well as laboratory dropping experiments with molten tin and water. The in-pile experiments are performed by Sandia Laboratories in the Annular Core Pulse Reactor (ACPR), which has a minimum period of 1.3 milliseconds. These single-pin experiments are performed in a piston-loaded, stagnant-sodium autoclave, that is conceptually similar to the one used in the S-11 TREAT test. Unlike the S-11 test, however, realistic radial temperature profiles are obtained in the fuel, the cladding, and the sodium by pre-pulsing the reactor about 1/2 second before the main pulse. A series of preparatory runs have been made with helium-filled capsules and at low energy with sodium-filled capsules. The first significant fuel-coolant interaction run is scheduled for late March 1976. This will be a double-pulsed run at 2700 j/gm UO 2 . A continuing series of experiments is planned with oxide and advanced fuels in both fresh and irradiated form. In molten-tin-water dropping experiments at UCLA, microsecond duration multi-flash photography has been used for event diagnostics. Transition or nucleate boiling was found to trigger energetic interactions or vapor explosions. Temperature stratification in the water was found to reduce the threshold tin temperature necessary to produce vapor explosions below that the predicted by the coolant homogeneous nucleation hypothesis. Interaction zone growth times of a few msec were measured

  17. CASL L1 Milestone report: CASL.P4.01, sensitivity and uncertainty analysis for CIPS with VIPRE-W and BOA

    International Nuclear Information System (INIS)

    Sung, Yixing; Adams, Brian M.; Secker, Jeffrey R.

    2011-01-01

    The CASL Level 1 Milestone CASL.P4.01, successfully completed in December 2011, aimed to 'conduct, using methodologies integrated into VERA, a detailed sensitivity analysis and uncertainty quantification of a crud-relevant problem with baseline VERA capabilities (ANC/VIPRE-W/BOA).' The VUQ focus area led this effort, in partnership with AMA, and with support from VRI. DAKOTA was coupled to existing VIPRE-W thermal-hydraulics and BOA crud/boron deposit simulations representing a pressurized water reactor (PWR) that previously experienced crud-induced power shift (CIPS). This work supports understanding of CIPS by exploring the sensitivity and uncertainty in BOA outputs with respect to uncertain operating and model parameters. This report summarizes work coupling the software tools, characterizing uncertainties, and analyzing the results of iterative sensitivity and uncertainty studies. These studies focused on sensitivity and uncertainty of CIPS indicators calculated by the current version of the BOA code used in the industry. Challenges with this kind of analysis are identified to inform follow-on research goals and VERA development targeting crud-related challenge problems.

  18. ESTUDIO DE LAS PROPIEDADES ESTRUCTURALES Y ELECTRÓNICAS DE LA FASE (P 4(2/mnm DEL MnO2

    Directory of Open Access Journals (Sweden)

    Wilmer Y. Córdoba

    2012-01-01

    Full Text Available Se reportan cálculos de primeros principios de las propiedades electrónicas del MnO 2 , el cual posee propiedades magnéticas debido a su configuración electrónica , por lo cual es apto para diversas aplicaciones a nivel tecnológico e industrial. Se calculan las propiedades estructurales y electrónicas en su fase P4(2/mnm, usando el formalismo de la Teoría de la Funcional de la Densidad (DFT con la aproximación LDA+U para tratar los efectos de la correlación fuerte y el método de ondas planas aumentadas y linealizadas (FP - LAPW, el cual se implementa en el software Wien2k . L os parámetros estructurales enco ntrados son: la constante de red , la energía de cohesión Además, se realizó un estudio detallado de las propiedades electrónicas por medio de la densidad de estados (DOS para obtener las características conductoras del material encontrando que este posee propiedades distintas de espín indicando que el material se comporta como de tipo Hall Metall .

  19. Use Electrospinning to Introduce Graphene into Poly(4-Vinylpridine) (P4VP) Polymer Fibers and Their Biocompatibility with Dental Pulp Stem Cells (DPSCs)

    Science.gov (United States)

    Zhang, Linxi; Chang, Chung-Chueh; Rafailovich, Miriam

    Graphene-polymer composite materials have been popularized in tissue engineering due to the outstanding thermal, electrical and mechanical properties of graphene. Most of the current studies, however, focus on 2-D structured films which hardly represent the real conditions of scaffolds in vivo environment and dispersion of graphene in polymer matrix has always been challenging since the graphene tends to aggregate. In our study, we have successfully introduced graphene nanoplatelets (GNPs) into poly(4-vinphylpridine) (P4VP) matrix and fabricated nano- and micro-scale size fibers by using electrospinning technique. SEM and TEM reveal uniform defect-free fiber structures and good dispersion of graphene; DSC and AFM indicate the enhancement of physical properties. The biocompatibility of the electrospun 3-D scaffolds with dental pulp stem cells (DPSCs) has been examined. Our results show that the cells can accelerate proliferation to respond to the existence of GNPs. SEM with EDAX reveals a deposition of mineralized calcium matrix on the fibers after 35-day incubation, which has possibly been caused by cell differentiation induced by fibrous scaffolds. Electrospinning Nano- and Mirco-scale size Poly(4-vinphylpridine) Fibers Loaded with Graphene Nano Platelets (GNPs).

  20. A semiempirical calculation of the fine and Zeeman structure of 4 p4 f and 4 p5 f configurations of Ge I. Gyromagnetic ratios

    Science.gov (United States)

    Anisimova, G. P.; Anisimov, Yu. I.; Gorbenko, A. P.; Dolmatova, O. A.; Krylov, I. R.; Mashek, I. Ch.; Zygankova, G. A.; Tchoffo, M.

    2017-04-01

    The gyromagnetic ratios ( g-factors) belong to the most important characteristics of atoms. For the 4 p4 f configuration of a germanium atom experimental values of g-factors are available only for four levels, while similar experimental data on the 4 p5 f configuration of Ge I are absent. Therefore, a theoretical study of the fine and Zeeman structures is topical for determining the gyromagnetic ratios. All the calculations are performed in the one-configuration approximation with the energy-operator matrix containing a maximum possible number of interactions, including magnetic: spin-orbit (own and other), spin-spin, and also orbitorbit interaction. The fine structure has been examined in three ( LS, LK, and jK) approximations in order to establish the nature of coupling in the systems studied and the reliability of g-factors. Apart from the g-factors, in studying the Zeeman splitting, its specific features—the crossing and anticrossing fields of magnetic components— have been determined. A comparative analysis of g-factors was performed that showed that our results are in agreement with the available, albeit few in number, experimental data. At all stages, the corresponding energy-operator matrices were numerically diagonalized, i.e., all the results presented in the paper were obtained in the intermediate coupling scheme.

  1. Analysis of valence XPS and AES of (PP, P4VP, PVME, PPS, PTFE) polymers by DFT calculations using the model molecules

    Science.gov (United States)

    Endo, Kazunaka; Shimada, Shingo; Kato, Nobuhiko; Ida, Tomonori

    2016-10-01

    We simulated valence X-ray photoelectron spectra (VXPS) of five [(CH2CH(CH3))n {poly(propyrene) PP}, ((CH2CH(C5NH4))n {poly(4-vinyl-pyridine) P4VP}, (CH2CHO(CH3))n {poly(vinyl methyl ether) PVME}, (C6H4S)n {poly(phenylene) sulphide PPS}, (CF2CF2)n {poly(tetrafluoroethylene) PTFE}] polymers by density-functional theory (DFT) calculations using the model oligomers. The spectra reflect the differences in the chemical structures between each polymer, since the peak intensities of valence band spectra are seen to be due to photo-ionization cross-section of (C, N, O, S, F) atoms by considering the orbital energies and cross-section values of the polymer models, individually. In the Auger electron spectra (AES) simulations, theoretical kinetic energies of the AES are obtained with our modified calculation method. The modified kinetic energies correspond to two final-state holes at the ground state and at the transition-state in DFT calculations, respectively. Experimental peaks of (C, N, O)- KVV, and S L2,3VV AES for each polymer are discussed in detail by our modified calculation method.

  2. Resolution of the diadenosine 5',5'''-P1,P4-tetraphosphate binding subunit from a multiprotein form of HeLa cell DNA polymerase α

    International Nuclear Information System (INIS)

    Baril, E.; Bonin, P.; Burstein, D.; Mara, K.; Zamecnik, P.

    1983-01-01

    A diadenosine 5',5'''-P 1 ,P 4 -tetraphosphate (Ap 4 A) binding subunit has been resolved from a high molecular weight (640,000) multiprotein form of DNA polymerase α [deoxy-nucleoside triphosphate:DNA nucleotidyltransferase (DNA-directed), EC 2.7.7.7] from HeLa cells. The Ap 4 A binding activity copurifies with the DNA polymerizing activity during the course of purification. Hydrophobic chromatograpy on butylagarose resolves the Ap 4 A binding activity from the DNA polymerase. The Ap 4 A binding activity is protein in nature since the binding of Ap 4 A is abolished by treatment of the isolated binding activity with proteinase K but is insensitive to treatment with DNase or RNase. The molecular weight of the Ap 4 A binding protein, as determined by polyacrylamide gel electrophoresis under nondenaturing conditions or by NaDodSO 4 /polyacrylamide gel electrophoresis after photoaffinity labeling of the protein with [ 32 P]Ap 4 A is 92,000 or 47,000. The binding activity of this protein is highly specific for Ap 4 A

  3. Monitoring 5p-4d soft X-ray emission of La when exciting through the low-lying 3d-4f threshold

    International Nuclear Information System (INIS)

    Moewes, A.; Wilks, R.; Kochur, A.G.; Kurmaev, E.Z.

    2005-01-01

    The intensity of the La 5p → 4d emission of La metal is being monitored while scanning across the deeper-lying 3d → 4f photoexcitation thresholds of the same atom. We find a strong resonant enhancement in the La 5p-4d fluorescence emission (around 83 eV) when exciting at the 3d → 4f resonances (829-852 eV). We show that the emission behavior is due to cascading decay of the resonantly excited 3d 9 4f +1 configuration. The number of 4d-vacancies increases immensely due to electronic cascades. By calculating the probability of the 5p → 4d emission resulting from cascading decay and then taking into account self-absorption of the emitted photons, we obtain good agreement with the experimental results. We also report an enhanced integral intensity in the 5p → 4d fluorescence, which we attribute to intra-atomic resonance processes

  4. CASL L1 Milestone report : CASL.P4.01, sensitivity and uncertainty analysis for CIPS with VIPRE-W and BOA.

    Energy Technology Data Exchange (ETDEWEB)

    Sung, Yixing (Westinghouse Electric Company LLC, Cranberry Township, PA); Adams, Brian M.; Secker, Jeffrey R. (Westinghouse Electric Company LLC, Cranberry Township, PA)

    2011-12-01

    The CASL Level 1 Milestone CASL.P4.01, successfully completed in December 2011, aimed to 'conduct, using methodologies integrated into VERA, a detailed sensitivity analysis and uncertainty quantification of a crud-relevant problem with baseline VERA capabilities (ANC/VIPRE-W/BOA).' The VUQ focus area led this effort, in partnership with AMA, and with support from VRI. DAKOTA was coupled to existing VIPRE-W thermal-hydraulics and BOA crud/boron deposit simulations representing a pressurized water reactor (PWR) that previously experienced crud-induced power shift (CIPS). This work supports understanding of CIPS by exploring the sensitivity and uncertainty in BOA outputs with respect to uncertain operating and model parameters. This report summarizes work coupling the software tools, characterizing uncertainties, and analyzing the results of iterative sensitivity and uncertainty studies. These studies focused on sensitivity and uncertainty of CIPS indicators calculated by the current version of the BOA code used in the industry. Challenges with this kind of analysis are identified to inform follow-on research goals and VERA development targeting crud-related challenge problems.

  5. Potential jamming of recirculation system valves in the safety injection system (SI) and containment spray (CS) systems for 1300 MW/P'4 PWRs

    International Nuclear Information System (INIS)

    Felisiak, Ph.

    2001-11-01

    By the end of the year 2000, an anomaly has been found in the recirculation system valves of the Safety Injection (SI) and Containment Spray (CS) systems on twelve French 1300 MWe/P'4 pressurized water reactors. This anomaly might block the valve and prevent its opening, especially in case of loss of coolant primary accident (LOCA), due to an operating stress exceeding the value considered for motorization sizing. The reason is a high overpressure in the valve body caused by a temperature rise of the water contained in the body ('thermal binding'). This fault constitutes a potential common-mode failure risk, which could cause the inoperability of the recirculation flow both redundant tracks of the SI and CS systems. The Institute for Protection and Nuclear Safety estimated the core damage risk in this situation at 3 x 10 -4 per unit per year. The emergency of processing the generic anomaly led the utility Electricite de France (EdF) to develop a modification in two steps (temporary solution and final solution). (author)

  6. Summary and evaluation: fuel dynamics loss-of-flow experiments (tests L2, L3, and L4)

    International Nuclear Information System (INIS)

    Barts, E.W.; Deitrich, L.W.; Eberhart, J.G.; Fischer, A.K.; Meek, C.C.

    1975-09-01

    Three similar experiments conducted to support the analyses of hypothetical LMFBR unprotected-loss-of-flow accidents are summarized and evaluated. The tests, designated L2, L3, and L4, provided experimental data against which accident-analysis codes could be compared, so as to guide further analysis and modeling of the initiating phases of the hypothetical accident. The tests were conducted using seven-pin bundles of mixed-oxide fuel pins in Mark-II flowing-sodium loops in the TREAT reactor. Test L2 used fresh fuel. Tests L3 and L4 used irradiated fuel pins having, respectively, ''intermediate-power'' (no central void) and ''high-power'' (fully developed central void) microstructure. 12 references

  7. Preparation of a diphosphine with persistent phosphinyl radical character in solution: characterization, reactivity with O2, S8, Se, Te, and P4, and electronic structure calculations.

    Science.gov (United States)

    Giffin, Nick A; Hendsbee, Arthur D; Roemmele, Tracey L; Lumsden, Michael D; Pye, Cory C; Masuda, Jason D

    2012-11-05

    A new, easily synthesized diphosphine based on a heterocyclic 1,3,2-diazaphospholidine framework has been prepared. Due to the large, sterically encumbering Dipp groups (Dipp = 2,6-diisopropylphenyl) on the heterocyclic ring, the diphosphine undergoes homolytic cleavage of the P-P bond in solution to form two phosphinyl radicals. The diphosphine has been reacted with O(2), S(8), Se, Te, and P(4), giving products that involve insertion of elements between the P-P bond to yield the related phosphinic acid anhydride, sulfide/disulfide, selenide, telluride, and a butterfly-type perphospha-bicyclobutadiene structure with a trans,trans-geometry. All molecules have been characterized by multinuclear NMR spectroscopy, elemental analysis, and single-crystal X-ray crystallography. Variable-temperature EPR spectroscopy was utilized to study the nature of the phosphinyl radical in solution. Electronic structure calculations were performed on a number of systems from the parent diphosphine [H(2)P](2) to amino-substituted [(H(2)N)(2)P](2) and cyclic amino-substituted [(H(2)C)(2)(NH)(2)P](2); then, bulky substituents (Ph or Dipp) were attached to the cyclic amino systems. Calculations on the isolated diphosphine at the B3LYP/6-31+G* level show that the homolytic cleavage of the P-P bond to form two phosphinyl radicals is favored over the diphosphine by ~11 kJ/mol. Furthermore, there is a significant amount of relaxation energy stored in the ligands (52.3 kJ/mol), providing a major driving force behind the homolytic cleavage of the central P-P bond.

  8. Molecular gallium arsenide phosphide clusters prepared from AsP(3), P(4), and [{GaC(SiMe(3))(3)}(4)].

    Science.gov (United States)

    Cossairt, Brandi M; Cummins, Christopher C

    2010-11-08

    Treatment of AsP(3) with 0.75 equivalents of [{GaC(SiMe(3))(3)}(4)] resulted in selective insertion of three equivalents of {GaC(SiMe(3))(3)} into the three As--P bonds to give [As{GaC(SiMe(3))(3)}(3)P(3)] (1-As) with an intact cyclo-P(3) ring. This yellow compound has been characterized by NMR spectroscopy, combustion analysis, single-crystal X-ray diffraction, UV/Vis spectroscopy, Raman spectroscopy, and cyclic voltammetry (THF, 0.2 M [TBA][B(C(6)F(5))(4)]; TBA=tetrabutyl ammonium). Computational models of 1-As and the isomeric [P{GaC(SiMe(3))(3)}(3)AsP(2)] (1-P) have been investigated as well, revealing several interesting electronic features of these cage molecules. Following from the cyclic voltammetry studies of 1-As that highlight an irreversible two-electron reduction at -2.2 V versus Fc/Fc(+), treatment with one equivalent of [Mg(C(14)H(10))(thf)(3)] resulted in two-electron reduction to provide [As{GaC(SiMe(3))(3)}(3)P(3)Mg(thf)(3)] (2), in which the Mg(2+) ion has inserted into one of the P--P bonds of the cyclo-P(3) ring. It was also found that treatment of AsP(3) or P(4) with one equivalent of [{GaC(SiMe(3))(3)}(4)] resulted in formation of the quadruple insertion products [As{GaC(SiMe(3))(3)}(4)P(3)] (3) and [P{GaC(SiMe(3))(3)}(4)P(3)] (4), respectively.

  9. Human rotavirus strains circulating in Venezuela after vaccine introduction: predominance of G2P[4] and reemergence of G1P[8].

    Science.gov (United States)

    Vizzi, Esmeralda; Piñeros, Oscar A; Oropeza, M Daniela; Naranjo, Laura; Suárez, José A; Fernández, Rixio; Zambrano, José L; Celis, Argelia; Liprandi, Ferdinando

    2017-03-21

    Rotavirus (RV) is the most common cause of severe childhood diarrhea worldwide. Despite Venezuela was among the first developing countries to introduce RV vaccines into their national immunization schedules, RV is still contributing to the burden of diarrhea. Concerns exist about the selective pressure that RV vaccines could exert on the predominant types and/or emergence of new strains. To assess the impact of RV vaccines on the genotype distribution 1 year after the vaccination was implemented, a total of 912 fecal specimens, collected from children with acute gastroenteritis in Caracas from February 2007 to April 2008, were screened, of which 169 (18.5%) were confirmed to be RV positive by PAGE. Rotavirus-associated diarrhea occurred all year-round, although prevailed during the coolest and driest months among unvaccinated children under 24 months old. Of 165 RV strains genotyped for G (VP7) and P (VP4) by seminested multiplex RT-PCR, 77 (46.7%) were G2P[4] and 63 (38.2%) G1P[8]. G9P[8], G3P[8] and G2P[6] were found in a lower proportion (7.3%). Remarkable was also the detection of rotaviruses, but they were rather distant from Rotarix ® vaccine and pre-vaccine strains. Unique amino acid substitutions observed on neutralization domains of the VP7 sequence from Venezuelan post-vaccine G1P[8] could have conditioned their re-emergence and a more efficient dissemination into susceptible population. The results suggest that natural fluctuations of genotypes in combination with forces driving the genetic evolution could determine the spread of novel strains, whose long-term effect on the efficacy of available vaccines should be determined.

  10. The P3 kimberlite and P4 lamproite, Wajrakarur kimberlite field, India: mineralogy, and major and minor element compositions of olivines as records of their phenocrystic vs xenocrystic origin

    Science.gov (United States)

    Shaikh, Azhar M.; Kumar, Satya P.; Patel, Suresh C.; Thakur, Satyajeet S.; Ravi, Subramanian; Behera, Duryadhan

    2018-03-01

    Distinctly different groundmass mineralogy characterise the hypabyssal facies, Mesoproterozoic diamondiferous P3 and P4 intrusions from the Wajrakarur Kimberlite Field, southern India. P3 is an archetypal kimberlite with macrocrysts of olivine and phlogopite set in a groundmass dominated by phlogopite and monticellite with subordinate amounts of serpentine, spinel, perovskite, apatite, calcite and rare baddeleyite. P4 contains mega- and macrocrysts of olivine set in a groundmass dominated by clinopyroxene and phlogopite with subordinate amounts of serpentine, spinel, perovskite, apatite, and occasional gittinsite, and is mineralogically interpreted as an olivine lamproite. Three distinct populations of olivine, phlogopite and clinopyroxene are recognized based on their microtextural and compositional characteristics. The first population includes glimmerite and phlogopite-clinopyroxene nodules, and Mg-rich olivine macrocrysts (Fo 90-93) which are interpreted to be derived from disaggregated mantle xenoliths. The second population comprises macrocrysts of phlogopite and Fe-rich olivine (Fo 81-89) from P3, megacrysts and macrocrysts of Fe-rich olivine (Fo 85-87) from P4 and a rare olivine-clinopyroxene nodule from P4 which are suggested to have a genetic link with the precursor melt of the respective intrusions. The third population represents clearly magmatic minerals such as euhedral phenocrysts of Fe-rich olivine (Fo 85-90) crystallised at mantle depths, and olivine overgrowth rims formed contemporaneously with groundmass minerals at crustal levels. Close spatial association and contemporaneous emplacement of P3 kimberlite and P4 lamproite is explained by a unifying petrogenetic model which involves the interaction of a silica-poor carbonatite melt with differently metasomatised wall rocks in the lithospheric mantle. It is proposed that the metasomatised wall rock for lamproite contained abundant MARID-type and phlogopite-rich metasomatic veins, while that for

  11. A note on p-groups of order ≤ p4p4p4

    Indian Academy of Sciences (India)

    . 2Department of Mathematics, University of ... However, the question of whether or not there is a p-group G with strict inequality c(G) = q(G) < p(G) is still open. ..... University Research Council for financial support. References. [1] Behravesh H ...

  12. Extending The P4P Agenda, Part 1: How Medicare Can Improve Patient Decision Making And Reduce Unnecessary Care: An agenda for Medicare to help drive improvements through pay-for-performance and shared decision making

    OpenAIRE

    Wennberg, John E.; O'Connor, Annette M.; Collins, E. Dale; Weinstein, James N.

    2007-01-01

    The decision to undergo many discretionary medical treatments should be based on informed patient choice. Shared decision making is an effective strategy for achieving this goal. The Centers for Medicare and Medicaid Services (CMS) should extend its pay-for-performance (P4P) agenda to assure that all Americans have access to a certified shared decision-making process. This paper outlines a strategy to achieve informed patient choice as the standard of practice for preference-sensitive care.

  13. ZPR-6 assembly 7 high {sup 240}Pu core experiments : a fast reactor core with mixed (Pu,U)-oxide fuel and a centeral high{sup 240}Pu zone.

    Energy Technology Data Exchange (ETDEWEB)

    Lell, R. M.; Morman, J. A.; Schaefer, R.W.; McKnight, R.D.; Nuclear Engineering Division

    2009-02-23

    ZPR-6 Assembly 7 (ZPR-6/7) encompasses a series of experiments performed at the ZPR-6 facility at Argonne National Laboratory in 1970 and 1971 as part of the Demonstration Reactor Benchmark Program (Reference 1). Assembly 7 simulated a large sodium-cooled LMFBR with mixed oxide fuel, depleted uranium radial and axial blankets, and a core H/D near unity. ZPR-6/7 was designed to test fast reactor physics data and methods, so configurations in the Assembly 7 program were as simple as possible in terms of geometry and composition. ZPR-6/7 had a very uniform core assembled from small plates of depleted uranium, sodium, iron oxide, U{sub 3}O{sub 8} and Pu-U-Mo alloy loaded into stainless steel drawers. The steel drawers were placed in square stainless steel tubes in the two halves of a split table machine. ZPR-6/7 had a simple, symmetric core unit cell whose neutronic characteristics were dominated by plutonium and {sup 238}U. The core was surrounded by thick radial and axial regions of depleted uranium to simulate radial and axial blankets and to isolate the core from the surrounding room. The ZPR-6/7 program encompassed 139 separate core loadings which include the initial approach to critical and all subsequent core loading changes required to perform specific experiments and measurements. In this context a loading refers to a particular configuration of fueled drawers, radial blanket drawers and experimental equipment (if present) in the matrix of steel tubes. Two principal core configurations were established. The uniform core (Loadings 1-84) had a relatively uniform core composition. The high {sup 240}Pu core (Loadings 85-139) was a variant on the uniform core. The plutonium in the Pu-U-Mo fuel plates in the uniform core contains 11% {sup 240}Pu. In the high {sup 240}Pu core, all Pu-U-Mo plates in the inner core region (central 61 matrix locations per half of the split table machine) were replaced by Pu-U-Mo plates containing 27% {sup 240}Pu in the plutonium

  14. Magnetic switch for reactor control rod. [LMFBR

    Science.gov (United States)

    Germer, J.H.

    1982-09-30

    A magnetic reed switch assembly is described for activating an electromagnetic grapple utilized to hold a control rod in position above a reactor core. In normal operation the magnetic field of a permanent magnet is short-circuited by a magnetic shunt, diverting the magnetic field away from the reed switch. The magnetic shunt is made of a material having a Curie-point at the desired release temperature. Above that temperature the material loses its ferromagnetic properties, and the magnetic path is diverted to the reed switch which closes and short-circuits the control circuit for the control rod electro-magnetic grapple which allows the control rod to drop into the reactor core for controlling the reactivity of the core.

  15. Reactivity control assembly for nuclear reactor. [LMFBR

    Science.gov (United States)

    Bollinger, L.R.

    1982-03-17

    This invention, which resulted from a contact with the United States Department of Energy, relates to a control mechanism for a nuclear reactor and, more particularly, to an assembly for selectively shifting different numbers of reactivity modifying rods into and out of the core of a nuclear reactor. It has been proposed heretofore to control the reactivity of a breeder reactor by varying the depth of insertion of control rods (e.g., rods containing a fertile material such as ThO/sub 2/) in the core of the reactor, thereby varying the amount of neutron-thermalizing coolant and the amount of neutron-capturing material in the core. This invention relates to a mechanism which can advantageously be used in this type of reactor control system.

  16. Automatic safety rod for reactors. [LMFBR

    Science.gov (United States)

    Germer, J.H.

    1982-03-23

    An automatic safety rod for a nuclear reactor containing neutron absorbing material and designed to be inserted into a reactor core after a loss-of-flow. Actuation is based upon either a sudden decrease in core pressure drop or the pressure drop decreases below a predetermined minimum value. The automatic control rod includes a pressure regulating device whereby a controlled decrease in operating pressure due to reduced coolant flow does not cause the rod to drop into the core.

  17. Generic considerations of LMFBR hypothetical accident energetics

    Energy Technology Data Exchange (ETDEWEB)

    Fauske, H.K.; Cho, D.H.; Epstein, M.; Grolmes, M.A.; Henry, R.E.

    1978-01-01

    The paper provides a preliminary assessment of generic accident energetics issues associated with alternatives relative to the reference (U,Pu) oxide fuel in liquid metal fast breeder reactors. The alternatives considered include thorium- and uranium-based oxide, carbide and metal fuel types. This assessment is made within the context of low probability, but potentially large consequence accidents, e.g., core-disruptive accidents.

  18. Dissolution of LMFBR fuel-sodium aerosols

    International Nuclear Information System (INIS)

    Allen, M.D.; Moss, O.R.

    1979-01-01

    Plutonium dioxide, normally insoluble in biological fluids, becomes much more soluble when mixed with sodium as the aerosol is formed. Sodium-fuel aerosols are approximately 20 times less soluble in simulated lung fluid than in distilled water. Solubility of sodium-fuel aerosols increases when Na 2 CO 3 are added to the distilled-water dissolution fluid. Mixed-oxide fuel aerosols without sodium present are relatively insoluble in distilled water, simulated lung fluid, and distilled water with Na 2 CO 3 and NaHCO 3 added

  19. Temperature measurements at the LMFBR core outlet

    International Nuclear Information System (INIS)

    Argous, J.P.; Berger, R.; Casejuane, R.; Fournier, C.; Girard, J.P.

    1980-04-01

    Over the last few years the temperature sensors used to measure the subassembly outlet temperature in French designed LMFBRs have been modified, basically in an effort to reduce the dispersion of the chromel-alumel thermocouple time constant, and to extend the frequency spectrum of the measurement signals by adding a steel electrode to from a stainless steel-sodium thermocouple. The result of this evolution is the temperature probe immersed in sodium which will be used in the SUPER PHENIX reactor. This paper describes the tests already completed or in progress on this probe. It also presents measurement data on the two basic probe parameters: the thermoelectric power of the stainless steel-sodium thermocouple and the time constant of the chromel-alumel thermocouple

  20. Transition phase in LMFBR hypothetical accidents

    International Nuclear Information System (INIS)

    Ostensen, R.W.; Henninger, R.J.; Jackson, J.F.

    1976-01-01

    Mechanistic analyses of transient-under-cooling accidents have led in some cases to a mild initiating phase instead of a direct hydrodynamic disassembly of the core. The fuel is then trapped in the core by the strong mechanical surroundings and blockages formed by refrozen cladding steel and/or fuel. The formation of fuel blockages has been verified experimentally. The bottled-up core will boil on fission and decay heat, with steel as the working fluid. Boil-up in a churn turbulent flow regime may prevent recriticality due to fuel recompaction. Ultimate fuel removal from the core is probably by a two-phase blow-down after permanent leakage paths are opened. However, a vigorous recriticality can not be precluded. Reactors with void coefficients larger than that in CRBR are more likely to disassemble in the initiating phase, so the transition phase may be unique to small cores

  1. Maintenance and repair of LMFBR steam generators

    International Nuclear Information System (INIS)

    Verriere, P.; Alanche, J.; Minguet, J.L.

    1984-06-01

    After some general remarks on the French fast neutron system, this paper presents the state of the program for the construction of fast reactor in France. Then, the general design of Super Phenix 1 steam generator components is outlined and, the in-service monitoring systems and protective devices with which they are equiped are briefly described. The methods used, in the event of leakage, for leak location, steam generator inspection, steam generator repair and putting the affected loop back into service, are discussed. There are two main lines of research, relating respectively to the means of water leak detection in sodium and the inspection arrangements that will be used either periodically, or following a sodium-water reaction. Finally, after a brief description of the steam generator, this paper describes the four incidents (leaks) that occurred on the Phenix steam generator in the course of 1982 and 1983, and the subsequent repair operations

  2. Response matrix method for large LMFBR analysis

    International Nuclear Information System (INIS)

    King, M.J.

    1977-06-01

    The feasibility of using response matrix techniques for computational models of large LMFBRs is examined. Since finite-difference methods based on diffusion theory have generally found a place in fast-reactor codes, a brief review of their general matrix foundation is given first in order to contrast it to the general strategy of response matrix methods. Then, in order to present the general method of response matrix technique, two illustrative examples are given. Matrix algorithms arising in the application to large LMFBRs are discussed, and the potential of the response matrix method is explored for a variety of computational problems. Principal properties of the matrices involved are derived with a view to application of numerical methods of solution. The Jacobi iterative method as applied to the current-balance eigenvalue problem is discussed

  3. Energetics of LMFBR core disruptive accidents

    International Nuclear Information System (INIS)

    Marchaterre, J.F.

    1979-01-01

    In general, in the design of fast reactor systems, containment design margins are specified by investigating the response of the containment to core disruptive accidents. The results of these analyses are then translated into criteria which the designers must meet. Currently, uniform and agreed upon criteria are lacking, and in this time while they are being developed, the designer should be aware of the considerations which go into the particular criteria he must work with, and participate in their development. This paper gives an overview of the current state of the art in assessing core disruptive accidents and the design implications of this process. (orig.)

  4. 4s24p3--4s4p4 and 4s24p3--4s2fp25s transitions in Y VII, Zr VIII, Nb IX, and MoX

    International Nuclear Information System (INIS)

    Reader, J.; Acquista, N.

    1981-01-01

    Spectra of ionized Y, Zr, Nb, and Mo have been observed in sliding-spark and triggered-spark discharges on 10.7-m normal- and grazing-incidence spectrographs at the National Bureau of Standards in Washington, D. C. From these observations the 4s 2 4p 3 --4s4p 4 transitions in Y VII, Zr VIII, Nb IX, and Mo X have been identified. The 4s 2 4p 3 --4s 2 4p 2 5s transitions in Y VII-Mo X, previously identified by Rahimullah et al. [Phys. Scr. 14, 221--223 (1976); 18, 96--106 (1978)], have been confirmed. In Y VII the 4s 2 4p 3 --4s 2 4p 2 6s and 4s4p 4 --4p 5 transition also have been found. The parameters obtained from least-squares fits to the energy levels are compared with Hartree--Fock calculations. Preliminary values of the ionization energies have been determined as 110.02 +- 0.15 eV for Y VII, 133.7 +- 0.5 eV for Zr VIII, 159.2 +- 0.7 eV for Nb IX, and 186.4 +- 1.2 eV for Mo X

  5. Halloysite Nanotubes Noncovalently Functionalised with SDS Anionic Surfactant and PS-b-P4VP Block Copolymer for Their Effective Dispersion in Polystyrene as UV-Blocking Nanocomposite Films

    Directory of Open Access Journals (Sweden)

    Lazaros Tzounis

    2017-01-01

    Full Text Available A simple and versatile method is reported for the noncovalent functionalisation of natural and “green” halloysite nanotubes (HNTs allowing their effective dispersion in a polystyrene (PS thermoplastic matrix via solvent mixing. Initially, HNTs (pristine HNTs were modified with physically adsorbed surfactant molecules of sodium dodecyl sulphate (SDS and PS-b-P4VP [P4VP: poly(4-vinylpyridine] block copolymer (BCP. Hereafter, SDS and BCP modified HNTs will be indicated as SDS-m-HNT and BCP-m-HNT. Nanocomposite films with 1, 2, and 5 wt.% HNT loadings were prepared, abbreviated as PS-SDS-m-HNT1, PS-SDS-m-HNT2, and PS-SDS-m-HNT5 and PS-BCP-m-HNT1, PS-BCP-m-HNT2, and PS-BCP-m-HNT5 (where 1, 2, and 5 correspond to the wt.% of HNTs. All nanocomposites depicted improved thermal degradation compared to the neat PS as revealed by thermogravimetric analysis (TGA. Transmission electron microscopy (TEM confirmed the good dispersion state of HNTs and the importance of modification by SDS and BCP. X-ray diffraction (XRD studies showed the characteristic interlayer spacing between the two silicate layers of pristine and modified HNTs. The PS/HNT nanocomposite films exhibited excellent ultraviolent-visible (UV-vis absorbance properties and their potential application as UV-filters could be envisaged.

  6. Comparison of GAP-3 and GAP-4 experiments with conduction freezing calculations

    International Nuclear Information System (INIS)

    Sienicki, J.J.; Spencer, B.W.

    1983-01-01

    Experiments GAP-3 and GAP-4 were performed at ANL to investigate the ability of molten fuel to penetrate downward through the narrow channels separating adjacent subassemblies during an LMFBR hypothetical core disruptive accident. Molten fuel-metal mixtures (81% UO 2 , 19% Mo) at an initial temperature of 3470 0 K generated by a thermite reaction were injected downward into 1 m long rectangular test sections (gap thickness = 0.43 cm, channel width = 20.3 cm) initially at 1170 0 K simulating the nominal Clinch River Breeder Reactor intersubassembly gap. In the GAP-3 test, a prolonged reaction time of approx. 15 s resulted in segregation of the metallic Mo and oxidic UO 2 constituents within the reaction vessel prior to injection. Consequently, Mo entered the test section first and froze, forming a complete plug at a penetration distance of 0.18 m. In GAP-4, the reaction time was reduced to approx. 3 s and the constituents remained well mixed upon injection with the result that the leading edge penetration distance increased to 0.35 m. Posttest examination of the cut-open test sections has revealed the existence of stable insulating crusts upon the underlying steel walls with melting and ablation of the walls only very localized

  7. MELCOR 1.8.2 assessment: Aerosol experiments ABCOVE AB5, AB6, AB7, and LACE LA2

    Energy Technology Data Exchange (ETDEWEB)

    Souto, F.J.; Haskin, F.E. [Univ. of New Mexico, Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Kmetyk, L.N. [Sandia National Labs., Albuquerque, NM (United States)

    1994-10-01

    The MELCOR computer code has been used to model four of the large-scale aerosol behavior experiments conducted in the Containment System Test Facility (CSTF) vessel. Tests AB5, AB6 and AB7 of the ABCOVE program simulate the dry aerosol conditions during a hypothetical severe accident in an LMFBR. Test LA2 of the LACE program simulates aerosol behavior in a condensing steam environment during a postulated severe accident in an LWR with failure to isolate the containment. The comparison of code results to experimental data show that MELCOR is able to correctly predict most of the thermal-hydraulic results in the four tests. MELCOR predicts reasonably well the dry aerosol behavior of the ABCOVE tests, but significant disagreements are found in the aerosol behavior modelling for the LA2 experiment. These results tend to support some of the concerns about the MELCOR modelling of steam condensation onto aerosols expressed in previous works. During these analyses, a limitation in the MELCOR input was detected for the specification of the aerosol parameters for more than one component. A Latin Hypercube Sampling (LHS) sensitivity study of the aerosol dynamic constants is presented for test AB6. The study shows the importance of the aerosol shape factors in the aerosol deposition behavior, and reveals that MELCOR input/output processing is highly labor intensive for uncertainty and sensitivity analyses based on LHS.

  8. TMPyP4 porphyrin distorts RNA G-quadruplex structures of the disease-associated r(GGGGCC)n repeat of the C9orf72 gene and blocks interaction of RNA-binding proteins.

    Science.gov (United States)

    Zamiri, Bita; Reddy, Kaalak; Macgregor, Robert B; Pearson, Christopher E

    2014-02-21

    Certain DNA and RNA sequences can form G-quadruplexes, which can affect genetic instability, promoter activity, RNA splicing, RNA stability, and neurite mRNA localization. Amyotrophic lateral sclerosis and frontotemporal dementia can be caused by expansion of a (GGGGCC)n repeat in the C9orf72 gene. Mutant r(GGGGCC)n- and r(GGCCCC)n-containing transcripts aggregate in nuclear foci, possibly sequestering repeat-binding proteins such as ASF/SF2 and hnRNPA1, suggesting a toxic RNA pathogenesis, as occurs in myotonic dystrophy. Furthermore, the C9orf72 repeat RNA was recently demonstrated to undergo the noncanonical repeat-associated non-AUG translation (RAN translation) into pathologic dipeptide repeats in patient brains, a process that is thought to depend upon RNA structure. We previously demonstrated that the r(GGGGCC)n RNA forms repeat tract length-dependent G-quadruplex structures that bind the ASF/SF2 protein. Here we show that the cationic porphyrin (5,10,15,20-tetra(N-methyl-4-pyridyl) porphyrin (TMPyP4)), which can bind some G-quadruplex-forming sequences, can bind and distort the G-quadruplex formed by r(GGGGCC)8, and this ablates the interaction of either hnRNPA1 or ASF/SF2 with the repeat. These findings provide proof of concept that nucleic acid binding small molecules, such as TMPyP4, can distort the secondary structure of the C9orf72 repeat, which may beneficially disrupt protein interactions, which may ablate either protein sequestration and/or RAN translation into potentially toxic dipeptides. Disruption of secondary structure formation of the C9orf72 RNA repeats may be a viable therapeutic avenue, as well as a means to test the role of RNA structure upon RAN translation.

  9. Crystallization and preliminary X-ray analysis of a putative sensor histidine kinase domain: the C-terminal domain of HksP4 from Aquifex aeolicus VF5

    International Nuclear Information System (INIS)

    Horita, Shoichiro; Yamanaka, Yosuke; Yamamura, Akihiro; Okada, Akitoshi; Nakayama, Jiro; Nagata, Koji; Tanokura, Masaru

    2011-01-01

    The putative sensor histidine kinase domain of the cytoplasmic protein HksP4 from the hyperthermophilic bacterium A. aeolicus VF5 was expressed, purified and crystallized by the sitting-drop vapour-diffusion method. Crystals were obtained in the presence of ATP and AMPPNP; they were found to belong to the same space group P2 1 2 1 2 1 and diffracted X-rays to 3.1 and 2.9 Å resolution, respectively. The histidine kinase domain of the cytoplasmic protein HksP4 from the hyperthermophilic bacterium Aquifex aeolicus VF5, located in the C-terminal half of the protein, was expressed, purified and crystallized. Diffraction-quality crystals were obtained in the presence of adenosine triphosphate (ATP) or adenosine 5′-(β,γ-imido)triphosphate (AMPPNP) by the sitting-drop vapour-diffusion method using PEG 3350 as the precipitant. The crystals obtained in the presence of ATP and AMPPNP diffracted X-rays to 3.1 and 2.9 Å resolution, respectively, on BL-5A at Photon Factory (Ibaraki, Japan) and were found to belong to the same space group P2 1 2 1 2 1 , with unit-cell parameters a = 80.2, b = 105.5, c = 122.0 Å and a = 81.5, b = 105.5, c = 130.9 Å, respectively. Their Matthews coefficients (V M = 2.74 and 2.51 Å 3 Da −1 , respectively) indicated that both crystals contained four protein molecules per asymmetric unit

  10. Would German physicians opt for pay-for-performance programs? A willingness-to-accept experiment in a large general practitioners' sample.

    Science.gov (United States)

    Krauth, Christian; Liersch, Sebastian; Jensen, Sören; Amelung, Volker Eric

    2016-02-01

    Implementing pay-for-performance (P4P) programs is a non-trivial task. As evaluation studies showed, P4P programs often failed to improve performance quality. A crucial element for the successful implementation of P4P is to gain acceptance with health care providers. The aim of our study was to determine, if (and at what bonus rate) German general practitioners (GPs) would participate in a P4P program. We further examined differences between respondents who would participate in a P4P program (participants) versus respondents who would not participate (non-participants). A mail survey was conducted among 2493 general practitioners (GPs) in Lower Saxony (with a response rate of 36.2%). The questionnaire addressed attitudes toward P4P and included a willingness to accept experiment concerning P4P implementation. The participation rate increased from 28% (at a bonus of 2.5%) to 50% (at a bonus of 20%). Participants showed better performance in target achievement and expected higher gains from P4P than non-participants. Major attitude differences were found in assessing feasibility of P4P, incentivizing performance and unintended consequences. The crucial factor for (not) accepting P4P might be the sense of (un)fairness of P4P. To convince GPs to participate in P4P, better evidence for the effectiveness of P4P is required. To address the concerns of GPs, future endeavors should be directed to tailoring P4P programs. Finally, program implementation must be well communicated and thoroughly discussed with health care providers. Copyright © 2016 Elsevier Ireland Ltd. All rights reserved.

  11. Alignment of Ar{sup +} [{sup 3}P]4p{sup 2}P{sup 0}{sub 3/2} satellite state from the polarization analysis of fluorescent radiation after photoionization

    Energy Technology Data Exchange (ETDEWEB)

    Yenen, O.; McLaughlin, K.W.; Jaecks, D.H. [Univ. of Nebraska, Lincoln, NE (United States)] [and others

    1997-04-01

    The measurement of the polarization of radiation from satellite states of Ar{sup +} formed after the photoionization of Ar provides detailed information about the nature of doubly excited states, magnetic sublevel cross sections and partial wave ratios of the photo-ejected electrons. Since the formation of these satellite states is a weak process, it is necessary to use a high flux beam of incoming photons. In addition, in order to resolve the many narrow doubly excited Ar resonances, the incoming photons must have a high resolution. The characteristics of the beam line 9.0.1 of the Advanced Light Source fulfill these requirements. The authors determined the polarization of 4765 {Angstrom} fluorescence from the Ar{sup +} [{sup 3}P] 4p {sup 2}P{sub 3/2}{sup 0} satellite state formed after photoionization of Ar by photons from the 9.0.1 beam line of ALS in the 35.620-38.261 eV energy range using a resolution of approximately 12,700. This is accomplished by measuring the intensities of the fluorescent light polarized parallel (I{parallel}) and perpendicular (I{perpendicular}) to the polarization axis of the incident synchrotron radiation using a Sterling Optics 105MB polarizing filter. The optical system placed at 90{degrees} with respect to the polarization axis of the incident light had a narrow band interference filter ({delta}{lambda}=0.3 nm) to isolate the fluorescent radiation.

  12. Distinct transmissibility features of TSE sources derived from ruminant prion diseases by the oral route in a transgenic mouse model (TgOvPrP4 overexpressing the ovine prion protein.

    Directory of Open Access Journals (Sweden)

    Jean-Noël Arsac

    Full Text Available Transmissible spongiform encephalopathies (TSEs are a group of fatal neurodegenerative diseases associated with a misfolded form of host-encoded prion protein (PrP. Some of them, such as classical bovine spongiform encephalopathy in cattle (BSE, transmissible mink encephalopathy (TME, kuru and variant Creutzfeldt-Jakob disease in humans, are acquired by the oral route exposure to infected tissues. We investigated the possible transmission by the oral route of a panel of strains derived from ruminant prion diseases in a transgenic mouse model (TgOvPrP4 overexpressing the ovine prion protein (A136R154Q171 under the control of the neuron-specific enolase promoter. Sources derived from Nor98, CH1641 or 87V scrapie sources, as well as sources derived from L-type BSE or cattle-passaged TME, failed to transmit by the oral route, whereas those derived from classical BSE and classical scrapie were successfully transmitted. Apart from a possible effect of passage history of the TSE agent in the inocula, this implied the occurrence of subtle molecular changes in the protease-resistant prion protein (PrPres following oral transmission that can raises concerns about our ability to correctly identify sheep that might be orally infected by the BSE agent in the field. Our results provide proof of principle that transgenic mouse models can be used to examine the transmissibility of TSE agents by the oral route, providing novel insights regarding the pathogenesis of prion diseases.

  13. Electron excitation cross sections for the 2s(2)2p(3)4S(O) -- 2s(2)2p(3)2D(O) (forbidden) and 4S(O) -- 2s2p(4) 4P (resonance) transitions in O II

    Science.gov (United States)

    Zuo, M.; Smith, Steven J.; Chutjian, A.; Williams, I. D.; Tayal, S. S.; Mclaughlin, Brendan M.

    1995-01-01

    Experimental and theoretical excitation cross sections are reported for the first forbidden transition 4S(O) -- 2S(2)2p(3) 2D(O) (lambda-lambda 3726, 3729) and the first allowed (resonance) transition 4S(O) -- 2s2p(4) 4P(lambda-833) in O II. Use is made of electron energy loss and merged-beams methods. The electron energy range covered is 3.33 (threshold) to 15 eV for the S -- D transition, and 14.9 (threshold) to 40 eV for the S -- P transition. Care was taken to assess and minimize the metastable fraction of the O II beam. An electron mirror was designed and tested to reflect inelastically backscattered electrons into the forward direction to account for the full range of polar scattering angles. Comparisons are made between present experiments and 11-state R-matrix calculations. Calculations are also presented for the 4S(O) -- 2s(2)2p(3)2P(O) (lambda-2470) transition.

  14. Visual in-pile fuel disruption experiments

    International Nuclear Information System (INIS)

    Cano, G.L.; Ostensen, R.W.; Young, M.F.

    1978-01-01

    In a loss-of-flow (LOF) accident in an LMFBR, the mode of disruption of fuel may determine the probability of a subsequent energetic excursion. To investigate these phenomena, in-pile disruption of fission-heated irradiated fuel pellets was recorded by high speed cinematography. Instead of fuel frothing or dust-cloud breakup (as used in the SAS code) massive and very rapid fuel swelling, not predicted by analytical models, occurred. These tests support massive fuel swelling as the initial mode of fuel disruption in a LOF accident. (author)

  15. Few-body experiments with polarized beams and polarized targets

    International Nuclear Information System (INIS)

    Simmons, J.E.

    1983-01-01

    A survey is presented concerning recent polarization experiments in the elastic p-d, p- 3 He, and p- 4 He systems. Mention is made of selected neutron experiments. The nominal energy range is 10 to 1000 MeV. Recent results and interpretations of the p-d system near 10 MeV are discussed. New experiments on the energy dependence of back angle p-d tensor polarization are discussed with respect to resolution of discrepancies and difficulty of theoretical interpretation. Progress is noted concerning multiple scattering interpretation of forward p-d deuteron polarization. Some new results are presented concerning the p- 3 He system and higher energy p- 4 He polarization experiments. 52 references

  16. Safety requirements and safety experience of nuclear facilities in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Schnurer, H.L.

    1977-01-01

    Peaceful use of nuclear energy within the F.R.G. is rapidly growing. The Energy Programme of the Federal Government forecasts a capacity of up to 50.000 MW in 1985. Whereas most of this capacity will be of the LWR-Type, other activities are related to LMFBR - and HTGR - development, nuclear ships, and facilities of the nuclear fuel cycle. Safety of nuclear energy is the pacemaker for the realization of nuclear programmes and projects. Due to a very high population - and industrialisation density, safety has the priority before economical aspects. Safety requirements are therefore extremely stringent, which will be shown for the legal, the technical as well as for the organizational area. They apply for each nuclear facility, its site and the nuclear energy system as a whole. Regulatory procedures differ from many other countries, assigning executive power to state authorities, which are supervised by the Federal Government. Another particularity of the regulatory process is the large scope of involvement of independent experts within the licensing procedures. The developement of national safety requirements in different countries generates a necessity to collaborate and harmonize safety and radiation protection measures, at least for facilities in border areas, to adopt international standards and to assist nuclear developing countries. However, different nationally, regional or local situations might raise problems. Safety experience with nuclear facilities can be concluded from the positive construction and operation experience, including also a few accidents and incidents and the conclusions, which have been drawn for the respective factilities and others of similar design. Another tool for safety assessments will be risk analyses, which are under development by German experts. Final, a scope of future problems and developments shows, that safety of nuclear installations - which has reached a high performance - nevertheless imposes further tasks to be solved

  17. Customer experience

    OpenAIRE

    Koperdáková, Zuzana

    2016-01-01

    Bachelor thesis deals with the theme of customer experience and terms related to this topic. The thesis consists of three parts. The first part explains the terms generally, as the experience or customer loyalty. The second part is dedicated to medotology used for Customer Experience Management. In the third part is described application of Customer Experience Management in practice, particularly in the context Touch Point Analyses in GE Money Bank.

  18. OPERA experiment

    International Nuclear Information System (INIS)

    Komatsu, M.

    2003-01-01

    OPERA is an accelerator experiment designed to explore Super-Kamiokande suggested ν μ ↔ν τ oscillation region in CNGS beam from CERN to LNGS. The key technique in OPERA is modern emulsion read out which applied to CHORUS and DONUT experiments. ECC technique which used in DONUT and OPERA has good modularity to enlarge apparatus for future Neutrino Factory experiments

  19. [Anaphylaxis due to peach with negative ImmunoCAP result to peach allergens, including rPru p 1, rPru p 3, AND rPru p 4: a report of two cases].

    Science.gov (United States)

    Maeda, Nobuko; Inomata, Naoko; Morita, Akiko; Kirino, Mio; Moriyama, Tatsuya; Ikezawa, Zenro

    2009-02-01

    We report two cases of anaphylactic reactions to peach with negative result of ImmunoCAP to peach. Case 1 is a 35-year-old man, who felt an itch in his oral cavity immediately after ingesting a whole fresh peach. He rapidly developed generalized urticaria, dyspnea, vomiting, and loss of consciousness. He recovered after treatment at a local hospital, thereafter he was referred to our hospital because ImmunoCAP conducted for screening allergens revealed a negative test result to peach and the cause of anaphylaxis remained unclear. He had a history of pollinosis. He reported that he previously felt an itch on his oral cavity after ingesting melon, watermelon, apple, and strawberry. Serum total IgE was 436 IU/ml. CAP-RAST revealed negative results to peach, strawberry and kiwi. Skin prick tests (SPTs) with raw peach pulp, canned peach pulp, strawberry and kiwi were positive. Case 2 is a 30-year-old woman who felt an itch on her oral cavity accompanied by blepharedema, rhinorrhea, generalized urticaria, nausea, abdominal pain and diarrhea after eating peach. She had a history of pollinosis. She reported that she previously developed urticaria after ingesting an apple. Serum total IgE was 85 IU/ml. ImmunoCAP revealed negative results to peach and apple. SPTs with canned yellow peach, strawberry and apple were positive. Consequently, the two patients were diagnosed with anaphylaxis due to peach, and allergic symptoms have never recurred since they avoided ingesting peach. Furthermore, in two patients ImmunoCAP to rPru p 1, rPru p 3, and rPru p 4 were negative. However, in IgE-immunoblotting of peach, serum IgE antibodies of two patients were bound to approximately 10 kDa proteins. Meanwhile, the cross-reactivity between Rosaceae fruits, such as peach, apple, apricot, and plum, has been reported. These results suggest that in patients, who are suspected of having peach anaphylaxis and show a negative ImmunoCAP result to peach, the additional testing, such as SPT with

  20. OPERA experiment

    CERN Document Server

    Komatsu, M

    2003-01-01

    OPERA is an accelerator experiment designed to explore Super- Kamiokande suggested nu//mu arrow left right nu//tau oscillation region in CNGS beam from CERN to LNGS. The key technique in OPERA is modern emulsion read out which applied to CHORUS and DONUT experiments. ECC technique which used in DONUT and OPERA has good modularity to enlarge apparatus for future Neutrino Factory experiments.

  1. Analyses for experiment on sodium-water reaction temperature by the CHAMPAGNE code

    International Nuclear Information System (INIS)

    Yoshioka, Naoki; Kishida, Masako; Yamada, Yumi

    2000-03-01

    In this work, analyses on sodium-water reaction temperature in the new SWAT-1(SWAT-1R) test were completed by the CHAMPAGNE code in order to understand void and velocity distribution in sodium system, which was difficult to be measured in experiments. The application method of the RELAP5/Mod2 code was investigated to LMFBR steam generator (SG) blow down analysis, too. The following results were obtained. (1) Analyses on sodium-water reaction temperature in the SWAT-1R test. 1) Analyses were carried out for the SWAT-1R test under the condition water leak rate 600 g/s by treating the pressure loss coefficient, the interface friction coefficient and the coefficient related to reaction rate as parameters. The effect and mechanism of each parameter on the shape of reaction zone were well understood by these analyses. 2) The void and velocity distribution in sodium system were estimated by use of the most suitable parameters. These analytical results are expected to be useful for planning of the SWAT-1R test and evaluation of test result. (2) Investigation of the RELAP5/Mod2 code. 1) The items to be improved in the RELAP5/Mod2 code were clarified to apply this code to the FBR SG blow down analysis. 2) One of these items was an addition of the shell-side (sodium-side) model. A sodium-side model was designed and added to the RELAP5/Mod2 code. Test calculations were carried out by this improved code and the basic function of this code was confirmed. (author)

  2. EEG activity in Carmelite nuns during a mystical experience.

    Science.gov (United States)

    Beauregard, Mario; Paquette, Vincent

    2008-10-17

    Mystical experiences relate to a fundamental dimension of human existence. These experiences, which are characterized by a sense of union with God, are commonly reported across all cultures. To date, no electroencephalography (EEG) study has been conducted to identify the neuroelectrical correlates of such experiences. The main objective of this study was to measure EEG spectral power and coherence in 14 Carmelite nuns during a mystical experience. EEG activity was recorded from 19 scalp locations during a resting state, a control condition and a mystical condition. In the mystical condition compared to control condition, electrode sites showed greater theta power at F3, C3, P3, Fz, Cz and Pz, and greater gamma1 power was detected at T4 and P4. Higher delta/beta ratio, theta/alpha ratio and theta/beta ratio were found for several electrode sites. In addition, FP1-C3 pair of electrodes displayed greater coherence for theta band while F4-P4, F4-T6, F8-T6 and C4-P4 pairs of electrodes showed greater coherence for alpha band. These results indicate that mystical experiences are mediated by marked changes in EEG power and coherence. These changes implicate several cortical areas of the brain in both hemispheres.

  3. TRIO experiment

    Energy Technology Data Exchange (ETDEWEB)

    Clemmer, R.G.; Finn, P.A.; Malecha, R.F.; Misra, B.; Billone, M.C.; Bowers, D.L.; Fischer, A.K.; Greenwood, L.R.; Mattas, R.F.; Tam, S.W.

    1984-09-01

    The TRIO experiment is a test of in-situ tritium recovery and heat transfer performance of a miniaturized solid breeder blanket assembly. The assembly (capsule) was monitored for temperature and neutron flux profiles during irradiation and a sweep gas flowed through the capsule to an anaytical train wherein the amounts of tritium in its various chemical forms were determined. The capsule was designed to operate at different temperatures and sweep gas conditions. At the end of the experiment the amount of tritium retained in the solid was at a concentration of less than 0.1 wppM. More than 99.9% of tritium generated during the experiment was successfully recovered. The results of the experiment showed that the tritium inventories at the beginning and at the end of the experiment follow a relationship which appears to be characteristic of intragranular diffusion.

  4. Pixel Experiments

    DEFF Research Database (Denmark)

    Petersen, Kjell Yngve; Søndergaard, Karin; Augustesen, Christina

    2015-01-01

    Pixel Experiments The term pixel is traditionally defined as any of the minute elements that together constitute a larger context or image. A pixel has its own form and is the smallest unit seen within a larger structure. In working with the potentials of LED technology in architectural lighting...... for using LED lighting in lighting design practice. The speculative experiments that have been set-up have aimed to clarify the variables that can be used as parameters in the design of lighting applications; including, for example, the structuring and software control of light. The experiments also...... elucidate and exemplify already well-known problems in relation to the experience of vertical and horizontal lighting. Pixel Experiments exist as a synergy between speculative test setups and lighting design in practice. This book is one of four books that is published in connection with the research...

  5. Collaborative experience

    DEFF Research Database (Denmark)

    Mortensen, Thomas Bøtker

    Literature review: Collaborative experience has been shown to have a positive effect on the collaborative outcome in general (Anand & Khanna, 2000; Kale, Dyer & Singh, 2002). Furthermore, it has been linked to the ability to exploit the network of the firm for learning (Powell, Koput and Smith...... experience was largest the higher the hypothesized ambiguity. Theoretically contribution: This research project aims at contributing to existing literature by arguing, that collaborative experience is a moderating variable which moderates the effects on collaborative outcome from the level of complexity......, that the largest effects from collaborative experience is from recent collaborative experience, since knowledge depreciates when it is not used. Methodologically contribution: The research project studies the dyad and aims at introducing, to this field of research, an established way of collecting data, a new...

  6. Mixture Experiments

    Energy Technology Data Exchange (ETDEWEB)

    Piepel, Gregory F.

    2007-12-01

    A mixture experiment involves combining two or more components in various proportions or amounts and then measuring one or more responses for the resulting end products. Other factors that affect the response(s), such as process variables and/or the total amount of the mixture, may also be studied in the experiment. A mixture experiment design specifies the combinations of mixture components and other experimental factors (if any) to be studied and the response variable(s) to be measured. Mixture experiment data analyses are then used to achieve the desired goals, which may include (i) understanding the effects of components and other factors on the response(s), (ii) identifying components and other factors with significant and nonsignificant effects on the response(s), (iii) developing models for predicting the response(s) as functions of the mixture components and any other factors, and (iv) developing end-products with desired values and uncertainties of the response(s). Given a mixture experiment problem, a practitioner must consider the possible approaches for designing the experiment and analyzing the data, and then select the approach best suited to the problem. Eight possible approaches include 1) component proportions, 2) mathematically independent variables, 3) slack variable, 4) mixture amount, 5) component amounts, 6) mixture process variable, 7) mixture of mixtures, and 8) multi-factor mixture. The article provides an overview of the mixture experiment designs, models, and data analyses for these approaches.

  7. Simulated experiments

    International Nuclear Information System (INIS)

    Bjerknes, R.

    1977-01-01

    A cybernetic model has been developed to elucidate some of the main principles of the growth regulation system in the epidermis of the hairless mouse. A number of actual and theoretical biological experiments have been simulated on the model. These included simulating the cell kinetics as measured by pulse labelling with tritiated thymidine and by continuous labelling with tritiated thymidine. Other simulated experiments included steady state, wear and tear, painting with a carcinogen, heredity and heredity and tumour. Numerous diagrams illustrate the results of these simulated experiments. (JIW)

  8. Researching experiences

    DEFF Research Database (Denmark)

    Gjedde, Lisa; Ingemann, Bruno

    , dialogue, moods, values and narratives have been investigated qualitatively with more than sixty informants in a range of projects. The processual methodological insights are put into a theoretical perspective and also presented as pragmatic dilemmas. Researching Experiences is relevant not only...... for students and researchers in media and communication studies but also for practitioners within the fields of media, communication and experience design....... for researching experiences in a variety of settings ranging from the museum, to news photography, and interactive media. The research led to the development of a set of methodological tools and approaches we term the reflexivity lab. The interaction in the experimental situation between the media and body...

  9. Researching experiences

    DEFF Research Database (Denmark)

    Gjedde, Lisa; Ingemann, Bruno

    In the beginning was - not the word - but the experience. This phenomenological approach provides the basis for this book, which focuses on how a person-in-situation experiences and constructs meaning from a variety of cultural visual events. This book presents video-based processual methods...... for researching experiences in a variety of settings ranging from the museum, to news photography, and interactive media. The research led to the development of a set of methodological tools and approaches we term the reflexivity lab. The interaction in the experimental situation between the media and body......, dialogue, moods, values and narratives have been investigated qualitatively with more than sixty informants in a range of projects. The processual methodological insights are put into a theoretical perspective and also presented as pragmatic dilemmas. Researching Experiences is relevant not only...

  10. Interpretive Experiments

    Science.gov (United States)

    DeHaan, Frank, Ed.

    1977-01-01

    Describes an interpretative experiment involving the application of symmetry and temperature-dependent proton and fluorine nmr spectroscopy to the solution of structural and kinetic problems in coordination chemistry. (MLH)

  11. Antimatter Experiments

    CERN Multimedia

    2004-01-01

    Antimatter should behave in identical fashion to matter if a form of spacetime symmetry called CPT invariance holds. Two experiments at CERN near Geneva are testing this hypothesis using antihydrogen atoms

  12. Media experiences

    DEFF Research Database (Denmark)

    Buhl, Mie

    2010-01-01

    on their particular iconic systems of meaning perceived through form, lines, contrasts, colours, structures textures, rhythm and composite qualities with embedded interdependent codes and culturally conditioned potential for construction of knowledge and meaning. Mediated experience adds new perspectives...

  13. Experiment Databases

    Science.gov (United States)

    Vanschoren, Joaquin; Blockeel, Hendrik

    Next to running machine learning algorithms based on inductive queries, much can be learned by immediately querying the combined results of many prior studies. Indeed, all around the globe, thousands of machine learning experiments are being executed on a daily basis, generating a constant stream of empirical information on machine learning techniques. While the information contained in these experiments might have many uses beyond their original intent, results are typically described very concisely in papers and discarded afterwards. If we properly store and organize these results in central databases, they can be immediately reused for further analysis, thus boosting future research. In this chapter, we propose the use of experiment databases: databases designed to collect all the necessary details of these experiments, and to intelligently organize them in online repositories to enable fast and thorough analysis of a myriad of collected results. They constitute an additional, queriable source of empirical meta-data based on principled descriptions of algorithm executions, without reimplementing the algorithms in an inductive database. As such, they engender a very dynamic, collaborative approach to experimentation, in which experiments can be freely shared, linked together, and immediately reused by researchers all over the world. They can be set up for personal use, to share results within a lab or to create open, community-wide repositories. Here, we provide a high-level overview of their design, and use an existing experiment database to answer various interesting research questions about machine learning algorithms and to verify a number of recent studies.

  14. Researching Experiences

    DEFF Research Database (Denmark)

    Gjedde, Lisa; Ingemann, Bruno

    In the beginning was - not the word - but the experience. This phenomenological approach provides the basis for this book, which focuses on how a person-in-situation experiences and constructs meaning from a variety of cultural visual events. This book presents video-based processual methods for ...... for students and researchers in media and communication studies but also for practitioners within the fields of media, communication and experience design.......In the beginning was - not the word - but the experience. This phenomenological approach provides the basis for this book, which focuses on how a person-in-situation experiences and constructs meaning from a variety of cultural visual events. This book presents video-based processual methods...... for researching experiences in a variety of settings ranging from the museum, to news photography, and interactive media. The research led to the development of a set of methodological tools and approaches we term the ReflexivityLab. The interaction in the experimental situation between the media and body...

  15. The experience of an experience

    DEFF Research Database (Denmark)

    Rasmussen, Alexandra Marie

    2016-01-01

    This paper examines a popular phenomenon that allows us to see ourselves from various perspectives, and allows us to perpetuate moments enabling us to relive experiences in a different state of mind or at a different time. To examine the phenomenon of experiencing an experience hermeneutic...... is a tool to create a particular mindset, in the developer, to generate a new way of thinking. This model is dynamic by nature and although it is not completed in every branch, it is complete in relation to experiencing your own experience. A company can apply the PoC to gain insight into primary...

  16. The Experiment

    Science.gov (United States)

    Mariana Nicoara, Floare

    2016-04-01

    My name is Nicoara Floarea and I am teacher at Secondary School Calatele and I teach students from preparatory class and the second grade . They are six-eight years old. In my activity, for introducing scientific concepts to my students, I use various and active methods or traditional methods including experiments. The experiment stimulates students' curiosity, their creativity, the understanding and knowledge taught accessibility. I propose you two such experiments: The life cycle of the plants (long-term experiment, with rigorous observation time):We use beans, wheat or other; They are grown in pots and on the cotton soaked with water,keeping under students' observation protecting them ( just soak them regularly) and we waiting the plants rise. For discussions and comments of plant embryo development we use the plants which rose on the cotton soaked with water plants at the end of the first week. Last school year we had in the pot climbing beans which in May made pods. They were not too great but our experiment was a success. The students could deduce that there will develop those big beans which after drying will be planted again. The influence of light on plants (average duration experiment with the necessary observation time): We use two pots in which plants are of the same type (two geraniums), one of them is situated so as to get direct sunlight and other plant we put in a closed box. Although we wet both plants after a week we see that the plant that benefited from sunlight has turned strain in direct sunlight, developing normally in return the plant out of the box I have yellowed leaves, photosynthesis does not She has occurred . Students will understand the vital role of the Sun in plants' life, both in the classroom and in nature. The experiment is a method of teaching students extremely pleasant, with a remarkable percentage of acquiring more knowledge.

  17. Pixel Experiments

    DEFF Research Database (Denmark)

    Søndergaard, Karin; Petersen, Kjell Yngve; Augustesen, Christina

    2015-01-01

    Pixel Experiments The term pixel is traditionally defined as any of the minute elements that together constitute a larger context or image. A pixel has its own form and is the smallest unit seen within a larger structure. In working with the potentials of LED technology in architectural lighting...... design it became relevant to investigate the use of LEDs as the physical equivalent of a pixel as a design approach. In this book our interest has been in identifying how the qualities of LEDs can be used in lighting applications. With experiences in the planning and implementation of architectural...... lighting design in practice, one quickly experiences and realises that there are untapped potentials in the attributes of LED technology. In this research, speculative studies have been made working with the attributes of LEDs in architectural contexts, with the ambition to ascertain new strategies...

  18. Researching Experiences

    DEFF Research Database (Denmark)

    Gjedde, Lisa; Ingemann, Bruno

    , dialogue, moods, values and narratives have been investigated qualitatively with more than sixty informants in a range of projects. The processual methodological insights are put into a theoretical perspective and also presented as pragmatic dilemmas.      Researching Experiences is relevant not only...... for students and researchers in media and communication studies but also for practitioners within the fields of media, communication and experience design....... for researching experiences in a variety of settings ranging from the museum, to news photography, and interactive media. The research led to the development of a set of methodological tools and approaches we term the ReflexivityLab. The interaction in the experimental situation between the media and body...

  19. EXPERIENCE WITH

    African Journals Online (AJOL)

    SURGERY DEPT

    Abstract. Background:Island flap techniques currently used in urethroplasty utilize the prepuce and the dorsal penile skin. Our experience with a one-stage island flap urethroplasty for urethral strictures utilizing the ventral penile skin is described. Patients and Method: This is a longitudinal study of seventy six consecutive ...

  20. Extending Experiences

    DEFF Research Database (Denmark)

    A computer game's player is experiencing not only the game as a designer-made artefact, but also a multitude of social and cultural practices and contexts of both computer game play and everyday life. As a truly multidisciplinary anthology, Extending Experiences sheds new light on the mesh...... of possibilities and influences the player engages with. Part one, Experiential Structures of Play, considers some of the key concepts commonly used to address the experience of a computer game player. The second part, Bordering Play, discusses conceptual and practical overlaps of games and everyday life...... and the impacts of setting up, crossing and breaking the boundaries of game and non-game. Part three, Interfaces of Play, looks at games as technological and historical artefacts and commodities. The fourth part, Beyond Design, introduces new models for the practical and theoretical dimensions of game design....