WorldWideScience

Sample records for s10fs-3 reactor

  1. Using S3 cloud storage with ROOT and CvmFS

    Science.gov (United States)

    Arsuaga-Ríos, María; Heikkilä, Seppo S.; Duellmann, Dirk; Meusel, René; Blomer, Jakob; Couturier, Ben

    2015-12-01

    Amazon S3 is a widely adopted web API for scalable cloud storage that could also fulfill storage requirements of the high-energy physics community. CERN has been evaluating this option using some key HEP applications such as ROOT and the CernVM filesystem (CvmFS) with S3 back-ends. In this contribution we present an evaluation of two versions of the Huawei UDS storage system stressed with a large number of clients executing HEP software applications. The performance of concurrently storing individual objects is presented alongside with more complex data access patterns as produced by the ROOT data analysis framework. Both Huawei UDS generations show a successful scalability by supporting multiple byte-range requests in contrast with Amazon S3 or Ceph which do not support these commonly used HEP operations. We further report the S3 integration with recent CvmFS versions and summarize the experience with CvmFS/S3 for publishing daily releases of the full LHCb experiment software stack.

  2. Single d-metal atoms on F(s) and F(s+) defects of MgO(001): a theoretical study across the periodic table.

    Science.gov (United States)

    Neyman, Konstantin M; Inntam, Chan; Matveev, Alexei V; Nasluzov, Vladimir A; Rösch, Notker

    2005-08-24

    Single d-metal atoms on oxygen defects F(s) and F(s+) of the MgO(001) surface were studied theoretically. We employed an accurate density functional method combined with cluster models, embedded in an elastic polarizable environment, and we applied two gradient-corrected exchange-correlation functionals. In this way, we quantified how 17 metal atoms from groups 6-11 of the periodic table (Cu, Ag, Au; Ni, Pd, Pt; Co, Rh, Ir; Fe, Ru, Os; Mn, Re; and Cr, Mo, W) interact with terrace sites of MgO. We found bonding with F(s) and F(s+) defects to be in general stronger than that with O2- sites, except for Mn-, Re-, and Fe/F(s) complexes. In M/F(s) systems, electron density is accumulated on the metal center in a notable fashion. The binding energy on both kinds of O defects increases from 3d- to 4d- to 5d-atoms of a given group, at variance with the binding energy trend established earlier for the M/O2- complexes, 4d period, group 7 atoms are slightly destabilized compared to their group 6 congeners in both the F(s) and F(s+) complexes; for later transition elements, the binding energy increases gradually up to group 10 and finally decreases again in group 11, most strongly on the F(s) site. This trend is governed by the negative charge on the adsorbed atoms. We discuss implications for an experimental detection of metal atoms on oxide supports based on computed core-level energies.

  3. Quick Look Report for Semiscale MOD-2C Test S-FS-2

    International Nuclear Information System (INIS)

    Boucher, T.J.; Chen, T.H.

    1985-01-01

    Results of a preliminary analysis of the first test performed in the Semiscale MOD-2C Steam Generator Feedwater and Steam Line Break (FS) experiment series are presented. Test S-FS-2 simulated a pressurized water reactor transient initiated by a double-ended offset shear of a steam generator main steam line upstream of the flow restrictor. Initial conditions represented normal ''hot-standby'' operation. The transient included an initial 600-s period in which only automatic plant protection systems responded to the initiating event. This period was followed by a series of operator actions necessary to stabilize the plant at conditions required to allow a natural circulation cooldown. The test results provided a measured evaluation of the effectiveness of the automatic responses in minimizing primary system overcooling and operator actions in stabilizing the plant. Test data also provided a basis for comparison with other tests in the series of the effects of break size on primary overcooling and primary-to-secondary heat transfer. 57 figs., 3 tabs

  4. Fs = μs Fn

    Directory of Open Access Journals (Sweden)

    Bruno Ministro

    2016-09-01

    Full Text Available http://dx.doi.org/10.5007/1807-9288.2016v12n1p195 Fs = μs Fn é uma releitura a três vozes dos Homeóstatos de José-Alberto Marques. Partindo do desmembramento e recomposição digital do material sonoro, testam-se, com base nas possibilidades oferecidas pelo cruzamento entre a plasticidade vocal e as ferramentas digitais de manipulação, as potencialidades combinatórias que uma obra desta natureza encerra.

  5. Controlling S2 terminal using FS software

    Science.gov (United States)

    Xue, Zhuhe

    New S2FS software for controlling S2 terminal of Sheshan station has been developed. It works under Field System software. All S2 operation commands are incorporated in a station program. The interface of SWT computer and S2 terminal is RS232 interface. S2FS software is designed by using Shell and C language. It has been used in VSOP experiments.

  6. Pretest analysis document for Test S-FS-7

    International Nuclear Information System (INIS)

    Hall, D.G.

    1985-06-01

    This report documents the pretest calculations completed for Semiscale Test S-FS-7. This test will simulate a transient initiated by a 14.3% break in a steam generator bottom feedwater line downstream of the check valve. The initial conditions represent normal operating conditions for a C-E System 80 nuclear power plant. Predictions of transients resulting from feedwater line breaks in these plants have indicated that significant primary system overpressurization may occur. The results of a RELAP5/MOD2/CY21 code calculation indicate that the test objectives for Test S-FS-7 can be achieved. The primary system overpressurization will occur but pose no threat to personnel or to plant integrity. 3 refs., 15 figs., 5 tabs

  7. Trichoderma reesei FS10-C enhances phytoremediation of Cd-contaminated soil by Sedum plumbizincicola and associated soil microbial activities

    Science.gov (United States)

    Teng, Ying; Luo, Yang; Ma, Wenting; Zhu, Lingjia; Ren, Wenjie; Luo, Yongming; Christie, Peter; Li, Zhengao

    2015-01-01

    This study aimed to explore the effects of Trichoderma reesei FS10-C on the phytoremediation of Cd-contaminated soil by the hyperaccumulator Sedum plumbizincicola and on soil fertility. The Cd tolerance of T. reesei FS10-C was characterized and then a pot experiment was conducted to investigate the growth and Cd uptake of S. plumbizincicola with the addition of inoculation agents in the presence and absence of T. reesei FS10-C. The results indicated that FS10-C possessed high Cd resistance (up to 300 mg L-1). All inoculation agents investigated enhanced plant shoot biomass by 6–53% of fresh weight and 16–61% of dry weight and Cd uptake by the shoots by 10–53% compared with the control. All inoculation agents also played critical roles in increasing soil microbial biomass and microbial activities (such as biomass C, dehydrogenase activity and fluorescein diacetate hydrolysis activity). Two inoculation agents accompanied by FS10-C were also superior to the inoculation agents, indicating that T. reesei FS10-C was effective in enhancing both Cd phytoremediation by S. plumbizincicola and soil fertility. Furthermore, solid fermentation powder of FS10-C showed the greatest capacity to enhance plant growth, Cd uptake, nutrient release, microbial biomass and activities, as indicated by its superior ability to promote colonization by Trichoderma. The solid fermentation powder of FS10-C might serve as a suitable inoculation agent for T. reesei FS10-C to enhance both the phytoremediation efficiency of Cd-contaminated soil and soil fertility. PMID:26113858

  8. Pretest analysis document for Test S-FS-11

    International Nuclear Information System (INIS)

    Hall, D.G.; Shaw, R.A.

    1985-07-01

    This report documents the pretest calculations completed for Semiscale Test S-FS-11. This test will simulate a transient initiated by a 50% break in a steam generator bottom feedwater line downstream of the check valve. The initial conditions represents normal operating conditions for a C-E System 80 nuclear plant. Prediction of transients resulting from feedwater line breaks in these plants have indicated that significant primary system overpressurization may occur. The results of a RELAP5/MOD2/CY21 code calculation indicate that the test objectives for Test S-FS-11 can be achieved. The primary system overpressurization will occur but pose no threat to personnel or plant integrity. 3 refs., 15 figs., 5 tabs

  9. Sub-fs electron bunch generation with sub-10-fs bunch arrival-time jitter via bunch slicing in a magnetic chicane

    Directory of Open Access Journals (Sweden)

    J. Zhu

    2016-05-01

    Full Text Available The generation of ultrashort electron bunches with ultrasmall bunch arrival-time jitter is of vital importance for laser-plasma wakefield acceleration with external injection. We study the production of 100-MeV electron bunches with bunch durations of subfemtosecond (fs and bunch arrival-time jitters of less than 10 fs, in an S-band photoinjector by using a weak magnetic chicane with a slit collimator. The beam dynamics inside the chicane is simulated by using two codes with different self-force models. The first code separates the self-force into a three-dimensional (3D quasistatic space-charge model and a one-dimensional coherent synchrotron radiation (CSR model, while the other one starts from the first principle with a so-called 3D sub-bunch method. The simulations indicate that the CSR effect dominates the horizontal emittance growth and the 1D CSR model underestimates the final bunch duration and emittance because of the very large transverse-to-longitudinal aspect ratio of the sub-fs bunch. Particularly, the CSR effect is also strongly affected by the vertical bunch size. Due to the coupling between the horizontal and longitudinal phase spaces, the bunch duration at the entrance of the last dipole magnet of the chicane is still significantly longer than that at the exit of the chicane, which considerably mitigates the impact of space charge and CSR effects on the beam quality. Exploiting this effect, a bunch charge of up to 4.8 pC in a sub-fs bunch could be simulated. In addition, we analytically and numerically investigate the impact of different jitter sources on the bunch arrival-time jitter downstream of the chicane, and define the tolerance budgets assuming realistic values of the stability of the linac for different bunch charges and compression schemes.

  10. Fast Spectrum Molten Salt Reactor Options

    Energy Technology Data Exchange (ETDEWEB)

    Gehin, Jess C [ORNL; Holcomb, David Eugene [ORNL; Flanagan, George F [ORNL; Patton, Bruce W [ORNL; Howard, Rob L [ORNL; Harrison, Thomas J [ORNL

    2011-07-01

    During 2010, fast-spectrum molten-salt reactors (FS-MSRs) were selected as a transformational reactor concept for light-water reactor (LWR)-derived heavy actinide disposition by the Department of Energy-Nuclear Energy Advanced Reactor Concepts (ARC) program and were the subject of a preliminary scoping investigation. Much of the reactor description information presented in this report derives from the preliminary studies performed for the ARC project. This report, however, has a somewhat broader scope-providing a conceptual overview of the characteristics and design options for FS-MSRs. It does not present in-depth evaluation of any FS-MSR particular characteristic, but instead provides an overview of all of the major reactor system technologies and characteristics, including the technology developments since the end of major molten salt reactor (MSR) development efforts in the 1970s. This report first presents a historical overview of the FS-MSR technology and describes the innovative characteristics of an FS-MSR. Next, it provides an overview of possible reactor configurations. The following design features/options and performance considerations are described including: (1) reactor salt options-both chloride and fluoride salts; (2) the impact of changing the carrier salt and actinide concentration on conversion ratio; (3) the conversion ratio; (4) an overview of the fuel salt chemical processing; (5) potential power cycles and hydrogen production options; and (6) overview of the performance characteristics of FS-MSRs, including general comparative metrics with LWRs. The conceptual-level evaluation includes resource sustainability, proliferation resistance, economics, and safety. The report concludes with a description of the work necessary to begin more detailed evaluation of FS-MSRs as a realistic reactor and fuel cycle option.

  11. Pretest analysis document for Test S-FS-6

    International Nuclear Information System (INIS)

    Shaw, R.A.; Hall, D.G.

    1985-05-01

    This report documents the pretest analyses completed for Semiscale Test S-FS-6. This test will simulate a transient initiated by a 100% break in a steam generator bottom feedwater line downstream of the check valve. The initial conditions represent normal operating conditions for a C-E System 80 nuclear power plant. Predictions of transients resulting from feedwater line breaks in these plants have indicated that significant primary system overpressurization may occur. The enclosed analyses include a RELAP5/MOD2/CY21 code calculation and preliminary results from a facility hot, integrated test which was conducted to near S-FS-6 specifications. The results of these analyses indicate that the test objectives for Test S-FS-6 can be achieved. The primary system overpressurization will pose no threat to personnel or plant integrity

  12. Quick look report for semiscale MOD-2C Test S-FS-11

    International Nuclear Information System (INIS)

    Plessinger, M.P.

    1985-11-01

    Results of a preliminary analysis of the fifth test performed in the Semiscale MOD-2C Steam Generator Feedwater and Steam Line Break (FS) experiment series are presented. Test S-FS-11 simulated a pressurized water reactor transient initiated by a 50% break in a steam generator bottom feedwater line downstream of the check valve. With the exception of primary pressure, the initial conditions represented the initial conditions used for the C-E System 80 Final Safety Analysis Report (FSAR) Appendix 15B calculations. The transient included an initial 600 s period in which only automatic plant protection systems responded to the initiating event. This period was followed by a series of operator actions necessary to stabilize the plant followed by break isolation and affected loop steam generator refill with auxiliary feedwater. The test results provided a measured evaluation of the effectiveness of the automatic responses in minimizing primary system overpressurization and operator actions in stabilizing the plant. Test data also provided a basis for comparison with other tests in the series of the effects of break size on primary overpressurization and primary-to-secondary heat transfer. 64 figs

  13. Study of core characteristics on fuel and coolant type. Results of F/S phase-I

    International Nuclear Information System (INIS)

    Ikegami, Tetsuo; Hayashi, Hideyuki; Sasaki, Makoto; Mizuno, Tomoyasu; Yamadate, Megumi; Takaki, Naoyuki; Kurosawa, Norifumi; Sakashita, Yoshiaki; Naganuma, Masayuki

    2001-03-01

    The phase-I of the Feasibility Study of Commercialized Fast Reactor Cycle Systems (F/S) were started from July, 1999 and terminated at the end of FY2000 in order to executed examination about technology alternatives of various commercialized fast reactor (FR) recycle concepts, in response to the JNC middle long term enterprise plan. In the phase-I of this F/S, a number of conceptual candidates have been selected from the following 5 viewpoints: a) ensuring safety, b) economic competitiveness to future LWRs, c) efficient utilization of resources, d) reduction of environmental burden, e) enhancement of nuclear non-proliferation. As for this study from the above viewpoints, core characteristics of many kinds of reactors have been investigated, analyzed and examined a core / a fuel characteristic in the combinations of fuel and coolant types and power output scales. Based on these results, R and D plans of the phase-II to be performed have been proposed, and a database to select candidate reactor concepts has been prepared. The conclusions have been obtained in the phase-I are as follows: (1) Evaluation of a fuel form in every each coolant was compared. A promising fuel form was extracted as follows: an oxide and a metal fuel for sodium coolant cores, a metal and a nitride fuel for heavy metal coolant cores, an oxide and a nitride fuel for carbon dioxide coolant cores and a nitride fuel for He gas coolant cores. (2) As the general idea that performance of a core nucleus can be compatible with re-criticality evasion in sodium coolant large-sized oxide fuel cores, a axial blanket particle elimination radial heterogeneous core is one influential candidate. (3) In case of Pb-Bi coolant nature circulation medium size core with an oxide fuel, it is difficult to simultaneously achieve higher discharged burn-up and higher breeding ratio according to the viewpoints of the phase-I. (4) Core characteristics of a carbon dioxide coolant core shows to be almost equivalent to that of

  14. Nb-base FS-85 Alloy as a Candidate Structural Material for Space Reactor Applications: Effects of Thermal Aging

    International Nuclear Information System (INIS)

    Leonard, Keith J.; Busby, Jeremy T.; Hoelzer, David T.; Zinkle, Steven J.

    2009-01-01

    The proposed use of fission reactors for manned or deep space missions have typically relied on the potential use of refractory metal alloys as structural materials. Throughout the history of these programs, the lead candidate has been Nb-1Zr due to its good fabrication and welding characteristics. However, the less than optimal creep resistance of this alloy has encouraged interest in the more complex FS-85 (Nb-28Ta-10W-1Zr) alloy. Despite this interest, a relatively small database exists for the properties of FS-85. These gaps include potential microstructural instabilities that can lead to mechanical property degradation. In this work, changes in microstructure and mechanical properties of FS-85 were investigated following 1100 h of thermal aging at 1098, 1248 and 1398 K. The changes in electrical resistivity, hardness and tensile properties between the as-annealed and aged materials are compared. Evaluation of the microstructural changes was performed through optical, scanning and transmission electron microscopy. The development of intragranular and grain boundary precipitation of Zr-rich compounds as a function of aging temperature was followed. Brittle tensile behavior was measured in the 1248 K aged material, while ductile behavior occurred in material aged above and below this temperature. The effect of temperature on the under and overaging of the grain boundary particles are believed to have contributed to the mechanical property behavior of the aged material

  15. Feasibility of processing the experimental breeder reactor-II driver fuel from the Idaho National Laboratory through Savannah River Site's H-Canyon facility

    Energy Technology Data Exchange (ETDEWEB)

    Magoulas, V. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-07-28

    Savannah River National Laboratory (SRNL) was requested to evaluate the potential to receive and process the Idaho National Laboratory (INL) uranium (U) recovered from the Experimental Breeder Reactor II (EBR-II) driver fuel through the Savannah River Site’s (SRS) H-Canyon as a way to disposition the material. INL recovers the uranium from the sodium bonded metallic fuel irradiated in the EBR-II reactor using an electrorefining process. There were two compositions of EBR-II driver fuel. The early generation fuel was U-5Fs, which consisted of 95% U metal alloyed with 5% noble metal elements “fissium” (2.5% molybdenum, 2.0% ruthenium, 0.3% rhodium, 0.1% palladium, and 0.1% zirconium), while the later generation was U-10Zr which was 90% U metal alloyed with 10% zirconium. A potential concern during the H-Canyon nitric acid dissolution process of the U metal containing zirconium (Zr) is the explosive behavior that has been reported for alloys of these materials. For this reason, this evaluation was focused on the ability to process the lower Zr content materials, the U-5Fs material.

  16. Nb-Base FS-85 Alloy as a Candidate Structural Material for Space Reactor Applications: Effects of Thermal Aging

    Science.gov (United States)

    Leonard, Keith J.; Busby, Jeremy T.; Hoelzer, David T.; Zinkle, Steven J.

    2009-04-01

    The proposed uses of fission reactors for manned or deep space missions have typically relied on the potential use of refractory metal alloys as structural materials. Throughout the history of these programs, a leading candidate has been Nb-1Zr, due to its good fabrication and welding characteristics. However, the less-than-optimal creep resistance of this alloy has encouraged interest in the more complex FS-85 (Nb-28Ta-10W-1Zr) alloy. Despite this interest, only a relatively small database exists for the properties of FS-85. Database gaps include the potential microstructural instabilities that can lead to mechanical property degradation. In this work, changes in the microstructure and mechanical properties of FS-85 were investigated following 1100 hours of thermal aging at 1098, 1248, and 1398 K. The changes in electrical resistivity, hardness, and tensile properties between the as-annealed and aged materials are compared. Evaluation of the microstructural changes was performed through optical microscopy (OM), scanning electron microscopy (SEM), and transmission electron microscopy (TEM). The development of intragranular and grain-boundary precipitation of Zr-rich compounds as a function of aging temperature was followed. Brittle tensile behavior was measured in the material aged at 1248 K, while ductile behavior occurred in samples aged above and below this temperature. The effect of temperature on the under- and overaging of the grain-boundary particles is believed to have contributed to the mechanical property behavior of the aged materials.

  17. SeaWiFS calibration and validation plan, volume 3

    International Nuclear Information System (INIS)

    Hooker, S.B.; Firestone, E.R.; Mcclain, C.R.; Esaias, W.E.; Barnes, W.; Guenther, B.; Endres, D.; Mitchell, B.G.; Barnes, R.

    1992-09-01

    The Sea-viewing Wide Field-of-view Sensor (SeaWiFS) will be the first ocean-color satellite since the Nimbus-7 Coastal Zone Color Scanner (CZCS), which ceased operation in 1986. Unlike the CZCS, which was designed as a proof-of-concept experiment, SeaWiFS will provide routine global coverage every 2 days and is designed to provide estimates of photosynthetic concentrations of sufficient accuracy for use in quantitative studies of the ocean's primary productivity and biogeochemistry. A review of the CZCS mission is included that describes that data set's limitations and provides justification for a comprehensive SeaWiFS calibration and validation program. To accomplish the SeaWiFS scientific objectives, the sensor's calibration must be constantly monitored, and robust atmospheric corrections and bio-optical algorithms must be developed. The plan incorporates a multi-faceted approach to sensor calibration using a combination of vicarious (based on in situ observations) and onboard calibration techniques. Because of budget constraints and the limited availability of ship resources, the development of the operational algorithms (atmospheric and bio-optical) will rely heavily on collaborations with the Earth Observing System (EOS), the Moderate Resolution Imaging Spectrometer (MODIS) oceans team, and projects sponsored by other agencies, e.g., the U.S. Navy and the National Science Foundation (NSF). Other elements of the plan include the routine quality control of input ancillary data (e.g., surface wind, surface pressure, ozone concentration, etc.) used in the processing and verification of the level-0 (raw) data to level-1 (calibrated radiances), level-2 (derived products), and level-3 (gridded and averaged derived data) products

  18. Design study on sodium-cooled middle-scale modular reactor

    International Nuclear Information System (INIS)

    Shimakawa, Yoshio; Nibe, Nobuaki; Hori, Toru

    2002-05-01

    In Phase 1 of the 'Feasibility Study on Commercialized Fast Reactor Cycle Systems (F/S)', an advanced loop type reactor has been selected as a promising concept of sodium-cooled middle-scale modular reactor, which has a possibility to fulfill the design requirements of the F/S. In Phase 2 of the F/S, it is planed to precede a preliminary conceptual design of a sodium-cooled middle-scale modular reactor based on the design of the advanced loop type reactor. Through the design study, it is intended to construct such a plant concept that can show its attraction and competitiveness as a commercialized reactor. This report summarizes the results of the design study on the sodium-cooled middle-scale modular reactor performed in JFY2001, which is the first year of Phase 2. As the construction cost of the sodium-cooled middle-scale modular reactor, which has been constructed in Phase 1, was about 10% higher than that of the sodium-cooled large-scale reactor, a new concept of the middle-scale modular reactor, which is expected to be equal to the large-scale reactor from a viewpoint of economic competitiveness, has been re-constructed based on the design of the advanced loop type reactor. After that, fundamental specifications of main systems and components for the new concept have been set, and critical subjects related to safety, structural integrity, thermal hydraulics, operability, maintainability and economy have been examined and evaluated. As a result of this study, the plant concept of the sodium-cooled middle-scale modular reactor has been constructed, which has a prospect to satisfy the economic goal (construction cost: less than 200,000 yens/kWe, etc.) and has a prospect to solve the critical subjects. From now on, reflecting the results of elemental experiments, the preliminary conceptual design of this plant will be preceded toward the selection for narrowing down candidate concepts at the end of Phase 2. (author)

  19. Study on image quality and dosage comparison of F/S system and DR system

    International Nuclear Information System (INIS)

    Kim, Sun Chil; Jung, Jae Eun

    2003-01-01

    Currently, many hospital are hastening to introduce digital radiography systems. This is a direct result of the intentions to improve medical services and to digitalized radiology information systems, and is also leading to the improvement of medical imaging technology. Throughout F/S system's long history, many people have researched the image quality and dosage concerning these systems, and as a result, huge improvements in the dosage of patients were possible. Similarly, I believe that DR systems need the same kind of effort. Of course, decreases in dosage that ignore image quality are unthinkable. The results of experiments conducted by five hospitals during a period of 3 months brought to us the conclusions listed below. Based on the comparison and analysis of the exposure control of F/S systems and DR systems, DR systems generally showed higher exposure control for parts of the phantom that became thicker, and the exposure control improved rapidly as the thickness increased. DR systems still proved to be somewhat deficient in resolution measurements compared to existing F/S systems. The image processing part of DR systems contributed much to these result. Under conditions used clinically, the dosage measurements of DR systems were generally higher regardless of region. According to the evaluation of image quality, DR systems showed a higher degree of satisfaction as the thickness of the region became thinner. As mentioned above and based on the mutual relationship experiments between the dosage and image quality of F/S systems and DR systems, research to increase the satisfaction of DR systems must be considered

  20. Neutron Radiography at the RP-10 reactor

    International Nuclear Information System (INIS)

    Hinostrosa, H.; Ravello, Y.; Cornejo, N.; Mendoza, M.; Montoya, M.

    1992-01-01

    The facility of neutron radiography at the RP-10 peruvian research reactor is described. The factor of collimation L/D is 149; the Cadmium ratio for the gold in the inspection's area is 4.5, and the thermal neutrons flux on the sample is 3,14 x 10 6 n/cm 2 s (author). 5 refs. 5 fig

  1. Pretest analysis document for Semiscale Test S-FS-1

    International Nuclear Information System (INIS)

    Chen, T.H.

    1985-02-01

    This report documents the pretest analysis calculation completed with the RELAP5/MOD2/CY21 code for Semiscale Test S-FS-1. The test will simulate the double-ended offset shear of the main steam line at the exit of the broken loop steam generator (downstream of the flow restrictor) and the subsequent plant recovery. The recovery portion of the test consists of a plant stabilization phase and a plant cooldown phase. The recovery procedures involve normal charging/letdown operation, pressurizer heater operation, secondary steam and feed of the unaffected steam generator, and pressurizer auxiliary spray. The test will be terminated after the unaffected steam generator and pressurizer pressures and liquid levels are stable, and the average priamry fluid temperature is stable at about 480 K (405 0 F) for at least 10 minutes

  2. InterProScan Result: FS758275 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS758275 FS758275_1_ORF2 2EC8961369A7A64F PANTHER PTHR11064:SF10 DNA POLYMERASE EPSILON P17 SUBUNIT (DNA POL...YMERASE EPSILON SUBUNIT 3) NA ? IPR009072 unintegrated Molecular Function: DNA binding (GO:0003677) ...

  3. InterProScan Result: FS827626 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS827626 FS827626_6_ORF2 2EC8961369A7A64F PANTHER PTHR11064:SF10 DNA POLYMERASE EPSILON P17 SUBUNIT (DNA POL...YMERASE EPSILON SUBUNIT 3) NA ? IPR009072 unintegrated Molecular Function: DNA binding (GO:0003677) ...

  4. Coulomb explosion of H2 induced by a sub-10 fs intense laser pulse

    International Nuclear Information System (INIS)

    Saugout, S.

    2006-12-01

    This work presents an experimental and theoretical study of the interaction of H2 with an intense sub-10 fs-laser pulse. The ejection of the two electrons of the molecule by the laser pulse leads to the fragmentation of the physical sys em in two protons. This process is called Coulomb Explosion. The electronic and nuclear dynamics can be analyzed by measuring the kinetic energy spectra as a function of different laser parameters. This dynamics is also analyzed through a non-perturbative, double active electron theoretical model, based on the resolution of the time dependent Schroedinger equation. In this model, the internuclear distance is treated as a quantum variable. The experimental and theoretical results enlight the translation of the kinetic energy spectra towards a higher energy when the pulse duration decreases. Experimentally, laser pulses from 40 to 10 fs were used and down to 1 fs using theoretical simulations. This study shows that, for laser pulses shorter than 4 fs, the carrier envelope phase becomes a crucial parameter. Furthermore, the molecular dynamics of H2 in intense laser field is sensitive to the peak intensity of the pulse. The experimental and theoretical results show that, as the intensity increases, the kinetic energy spectra are centered around a higher energy. In addition, the presence of two double ionization regimes is theoretically demonstrated for a pulse duration of 4 fs. The H 2 molecule is also sensitive to the temporal shape of the laser pulse. This sensitivity allows for the detection of pre- or post-pulses by measuring the experimental kinetic energy spectra. Finally, the different double ionization processes are studied. The results show that the electron rescattering influences the femtosecond nuclear dynamics. (author)

  5. All-fiber interferometer-based repetition-rate stabilization of mode-locked lasers to 10-14-level frequency instability and 1-fs-level jitter over 1  s.

    Science.gov (United States)

    Kwon, Dohyeon; Kim, Jungwon

    2017-12-15

    We report on all-fiber Michelson interferometer-based repetition-rate stabilization of femtosecond mode-locked lasers down to 1.3×10 -14 frequency instability and 1.4 fs integrated jitter in a 1 s time scale. The use of a compactly packaged 10 km long single-mode fiber (SMF)-28 fiber link as a timing reference allows the scaling of phase noise at a 10 GHz carrier down to -80  dBc/Hz at 1 Hz Fourier frequency. We also tested a 500 m long low-thermal-sensitivity fiber as a reference and found that, compared to standard SMF-28 fiber, it can mitigate the phase noise divergence by ∼10  dB/dec in the 0.1-1 Hz Fourier frequency range. These results suggest that the use of a longer low-thermal-sensitivity fiber may achieve sub-femtosecond integrated timing jitter with sub-10 -14 -level frequency instability in repetition rate by a simple and robust all-fiber-photonic method.

  6. Influence of remaining fission products in low-decontaminated fuel on reactor core characteristics

    International Nuclear Information System (INIS)

    Ohki, Shigeo

    2002-07-01

    Design study of core, fuel and related fuel cycle system with low-decontaminated fuel has been performed in the framework of the feasibility study (F/S) on commercialized fast reactor cycle systems. This report summarizes the influence on core characteristics of remaining fission products (FPs) in low-decontaminated fuel related to the reprocessing systems nominated in F/S phase I. For simple treatment of the remaining FPs in core neutronics calculation the representative nuclide method parameterized by the FP equivalent coefficient and the FP volume fraction was developed, which enabled an efficient evaluation procedure. As a result of the investigation on the sodium cooled fast reactor with MOX fuel designed in fiscal year 1999, it was found that the pyrochemical reprocessing with molten salt (the RIAR method) brought the largest influence. Nevertheless, it was still within the allowable range. Assuming an infinite-times recycling, the alternations in core characteristics were evaluated as follows: increment of burnup reactivity by 0.5%Δk/kk', decrement of breeding ratio by 0.04, increment of sodium void reactivity by 0.1x10 -2 Δk/kk' and decrement of Doppler constant (in absolute value) by 0.7x10 -3 Tdk/dT. (author)

  7. Functional analysis of Waardenburg syndrome-associated PAX3 and SOX10 mutations: report of a dominant-negative SOX10 mutation in Waardenburg syndrome type II.

    Science.gov (United States)

    Zhang, Hua; Chen, Hongsheng; Luo, Hunjin; An, Jing; Sun, Lin; Mei, Lingyun; He, Chufeng; Jiang, Lu; Jiang, Wen; Xia, Kun; Li, Jia-Da; Feng, Yong

    2012-03-01

    Waardenburg syndrome (WS) is an auditory-pigmentary disorder resulting from melanocyte defects, with varying combinations of sensorineural hearing loss and abnormal pigmentation of the hair, skin, and inner ear. WS is classified into four subtypes (WS1-WS4) based on additional symptoms. PAX3 and SOX10 are two transcription factors that can activate the expression of microphthalmia-associated transcription factor (MITF), a critical transcription factor for melanocyte development. Mutations of PAX3 are associated with WS1 and WS3, while mutations of SOX10 cause WS2 and WS4. Recently, we identified some novel WS-associated mutations in PAX3 and SOX10 in a cohort of Chinese WS patients. Here, we further identified an E248fsX30 SOX10 mutation in a family of WS2. We analyzed the subcellular distribution, expression and in vitro activity of two PAX3 mutations (p.H80D, p.H186fsX5) and four SOX10 mutations (p.E248fsX30, p.G37fsX58, p.G38fsX69 and p.R43X). Except H80D PAX3, which retained partial activity, the other mutants were unable to activate MITF promoter. The H80D PAX3 and E248fsX30 SOX10 were localized in the nucleus as wild type (WT) proteins, whereas the other mutant proteins were distributed in both cytoplasm and nucleus. Furthermore, E248fsX30 SOX10 protein retained the DNA-binding activity and showed dominant-negative effect on WT SOX10. However, E248fsX30 SOX10 protein seems to decay faster than the WT one, which may underlie the mild WS2 phenotype caused by this mutation.

  8. InterProScan Result: FS827626 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS827626 FS827626_6_ORF2 2EC8961369A7A64F PANTHER PTHR11064:SF10 DNA POLYMERASE EPSILON P17 SUBUNIT (DNA POL...YMERASE EPSILON SUBUNIT 3) 9e-35 T IPR009072 unintegrated Molecular Function: DNA binding (GO:0003677) ...

  9. InterProScan Result: FS758275 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS758275 FS758275_1_ORF2 2EC8961369A7A64F PANTHER PTHR11064:SF10 DNA POLYMERASE EPSILON P17 SUBUNIT (DNA POL...YMERASE EPSILON SUBUNIT 3) 9e-35 T IPR009072 unintegrated Molecular Function: DNA binding (GO:0003677) ...

  10. Research reactor`s role in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Choi, C-O [Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)

    1996-12-31

    After a TRIGA MARK-II was constructed in 1962, new research activity of a general nature, utilizing neutrons, prevailed in Korea. Radioisotopes produced from the MARK-II played a good role in the 1960`s in educating people as to what could be achieved by a neutron source. Because the research reactor had implanted neutron science in the country, another TRIGA MARK-III had to be constructed within 10 years after importing the first reactor, due to increased neutron demand from the nuclear community. With the sudden growth of nuclear power, however, the emphasis of research changed. For a while research activities were almost all oriented to nuclear power plant technology. However, the specifics of nuclear power plant technology created a need for a more highly capable research reactor like HANARO 30MWt. HANARO will perform well with irradiation testing and other nuclear programs in the future, including: production of key radioisotopes, doping of silicon by transmutation, neutron activation analysis, neutron beam experiments, cold neutron source. 3 tabs., 2 figs.

  11. EST Table: FS853636 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS853636 E_FL_fner_46O23_F_0 10/09/28 50 %/122 aa gb|EFA10616.1| hypothetical prote...GAP010623-PA Protein|3L:7358821:7360505:1|gene:AGAP010623 10/09/10 low homology 10/09/10 50 %/122 aa gi|2700

  12. Design study on sodium-cooled large-scale reactor

    International Nuclear Information System (INIS)

    Shimakawa, Yoshio; Nibe, Nobuaki; Hori, Toru

    2002-05-01

    In Phase 1 of the 'Feasibility Study on Commercialized Fast Reactor Cycle Systems (F/S)', an advanced loop type reactor has been selected as a promising concept of sodium-cooled large-scale reactor, which has a possibility to fulfill the design requirements of the F/S. In Phase 2 of the F/S, it is planed to precede a preliminary conceptual design of a sodium-cooled large-scale reactor based on the design of the advanced loop type reactor. Through the design study, it is intended to construct such a plant concept that can show its attraction and competitiveness as a commercialized reactor. This report summarizes the results of the design study on the sodium-cooled large-scale reactor performed in JFY2001, which is the first year of Phase 2. In the JFY2001 design study, a plant concept has been constructed based on the design of the advanced loop type reactor, and fundamental specifications of main systems and components have been set. Furthermore, critical subjects related to safety, structural integrity, thermal hydraulics, operability, maintainability and economy have been examined and evaluated. As a result of this study, the plant concept of the sodium-cooled large-scale reactor has been constructed, which has a prospect to satisfy the economic goal (construction cost: less than 200,000yens/kWe, etc.) and has a prospect to solve the critical subjects. From now on, reflecting the results of elemental experiments, the preliminary conceptual design of this plant will be preceded toward the selection for narrowing down candidate concepts at the end of Phase 2. (author)

  13. EST Table: FS920882 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available DICTED: similar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] gb|EEZ97704.1| budding uninhibited by benzimida...|91091890|ref|XP_970295.1| PREDICTED: similar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] FS920882 fufe ... ...zoles 3 [Tribolium castaneum] 10/09/13 61 %/256 aa FBpp0282833|DpseGA20454-PA 10/08

  14. EST Table: FS873739 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS873739 E_FL_fner_51P23_R_0 10/09/28 100 %/172 aa ref|NP_001037572.1| translationa...pp0225303|DvirGJ10886-PA 10/08/29 44 %/180 aa F25H2.11#CE09656#WBGene00009122#locus:tct-1#TCTP protein#statu...s:Confirmed#UniProt:Q93573#protein_id:CAB02 099.1 10/09/10 73 %/172 aa AGAP002667

  15. EST Table: FS932533 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS932533 E_FL_fwgP_34I10_F_0 10/09/28 96 %/124 aa ref|NP_001129358.1| osiris 21 [Bo...mbyx mori] gb|ACI23616.1| osiris 21 [Bombyx mori] 10/09/13 n.h 10/08/29 n.h 10/09/10 low homology 10/09/10 n.h 10/09/10 n.h FS930345 fwgP ...

  16. EST Table: FS930675 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS930675 E_FL_fwgP_28O10_F_0 10/09/28 40 %/120 aa ref|NP_001129360.1| osiris 9 [Bom...byx mori] gb|ACI23620.1| osiris 9 [Bombyx mori] 10/09/13 n.h 10/08/29 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS935058 fwgP ...

  17. EST Table: FS934649 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS934649 E_FL_fwgP_40K10_F_0 10/09/28 31 %/210 aa ref|NP_001129360.1| osiris 9 [Bom...byx mori] gb|ACI23620.1| osiris 9 [Bombyx mori] 10/09/13 n.h 10/08/29 n.h 10/09/10 low homology 10/09/10 n.h 10/09/10 n.h FS923180 fwgP ...

  18. EST Table: FS809383 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS809383 E_FL_fmgV_28P15_F_0 10/09/28 91 %/173 aa ref|NP_001036831.1| saposin-relat...29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 39 %/158 aa gi|91077504|ref|XP_966852.1| PREDICTED: similar to saposin isoform 1 [Tribolium castaneum] FS791050 fmgV ...

  19. EST Table: FS828361 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS828361 E_FL_fmgV_28P15_R_0 10/09/28 92 %/173 aa ref|NP_001036831.1| saposin-relat...29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 39 %/158 aa gi|91077504|ref|XP_966852.1| PREDICTED: similar to saposin isoform 1 [Tribolium castaneum] FS895586 fmgV ...

  20. EST Table: FS935181 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS935181 E_FL_fwgP_42D15_F_0 10/09/28 40 %/118 aa ref|NP_001129360.1| osiris 9 [Bom...byx mori] gb|ACI23620.1| osiris 9 [Bombyx mori] 10/09/13 n.h 10/08/29 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS935058 fwgP ...

  1. EST Table: FS930504 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS930504 E_FL_fwgP_28G04_F_0 10/09/28 40 %/120 aa ref|NP_001129360.1| osiris 9 [Bom...byx mori] gb|ACI23620.1| osiris 9 [Bombyx mori] 10/09/13 n.h 10/08/29 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS935058 fwgP ...

  2. EST Table: FS938424 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS938424 E_FL_fwgP_51P06_F_0 10/09/28 39 %/128 aa ref|NP_001129360.1| osiris 9 [Bom...byx mori] gb|ACI23620.1| osiris 9 [Bombyx mori] 10/09/13 n.h 10/08/29 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS935058 fwgP ...

  3. EST Table: FS924814 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS924814 E_FL_fwgP_11K20_F_0 10/09/28 39 %/114 aa ref|NP_001129360.1| osiris 9 [Bom...byx mori] gb|ACI23620.1| osiris 9 [Bombyx mori] 10/09/13 n.h 10/08/29 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS935058 fwgP ...

  4. EST Table: FS938378 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS938378 E_FL_fwgP_51N02_F_0 10/09/28 40 %/120 aa ref|NP_001129360.1| osiris 9 [Bom...byx mori] gb|ACI23620.1| osiris 9 [Bombyx mori] 10/09/13 n.h 10/08/29 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS935058 fwgP ...

  5. EST Table: FS933330 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS933330 E_FL_fwgP_36M07_F_0 10/09/28 100 %/103 aa ref|NP_001129360.1| osiris 9 [Bo...mbyx mori] gb|ACI23620.1| osiris 9 [Bombyx mori] 10/09/13 n.h 10/08/29 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS930560 fwgP ...

  6. EST Table: FS915156 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS915156 E_FL_fufe_34G19_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  7. EST Table: FS906636 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS906636 E_FL_fufe_08M11_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  8. EST Table: FS917709 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS917709 E_FL_fufe_42C09_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  9. EST Table: FS908946 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS908946 E_FL_fufe_15L23_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  10. EST Table: FS914517 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS914517 E_FL_fufe_32I12_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  11. EST Table: FS911186 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS911186 E_FL_fufe_22H12_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  12. EST Table: FS917981 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS917981 E_FL_fufe_42P12_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  13. EST Table: FS912711 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS912711 E_FL_fufe_27A14_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  14. EST Table: FS916402 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS916402 E_FL_fufe_38D15_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  15. EST Table: FS919976 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS919976 E_FL_fufe_48P22_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/13 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  16. EST Table: FS911993 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS911993 E_FL_fufe_24O22_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  17. EST Table: FS912253 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS912253 E_FL_fufe_25L04_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  18. EST Table: FS917956 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS917956 E_FL_fufe_42O09_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  19. EST Table: FS917447 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS917447 E_FL_fufe_41G05_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  20. EST Table: FS914674 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS914674 E_FL_fufe_32P17_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  1. EST Table: FS917785 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS917785 E_FL_fufe_42F24_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  2. EST Table: FS904384 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS904384 E_FL_fufe_01N19_F_0 10/09/28 100 %/164 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  3. EST Table: FS904587 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS904587 E_FL_fufe_02H08_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  4. EST Table: FS919260 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS919260 E_FL_fufe_46M19_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/13 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  5. EST Table: FS908267 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS908267 E_FL_fufe_13L04_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  6. EST Table: FS912841 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS912841 E_FL_fufe_27H01_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  7. EST Table: FS905814 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS905814 E_FL_fufe_06D23_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  8. EST Table: FS912585 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS912585 E_FL_fufe_26K20_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  9. EST Table: FS919646 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS919646 E_FL_fufe_47P17_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/13 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  10. EST Table: FS908281 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS908281 E_FL_fufe_13L21_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  11. EST Table: FS906986 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS906986 E_FL_fufe_09N12_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  12. InterProScan Result: FS826604 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS826604 FS826604_5_ORF1 1C8DFE9F04A27A5C PRINTS PR00385 P450 2.3e-10 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  13. EST Table: FS893327 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS893327 E_FL_ftes_11B24_R_0 10/09/28 87 %/134 aa ref|NP_001036831.1| saposin-relat...mology 10/09/10 35 %/119 aa gi|91077504|ref|XP_966852.1| PREDICTED: similar to saposin isoform 1 [Tribolium castaneum] FS895586 ftes ...

  14. EST Table: FS737373 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS737373 E_FL_bmmt_08K06_R_0 10/09/28 37 %/161 aa ref|XP_002067709.1| GK12566 [Dros...ophila willistoni] gb|EDW78695.1| GK12566 [Drosophila willistoni] 10/09/03 37 %/161 aa FBpp0241709|DwilGK12566-PA 10/08/28 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS737272 bmmt ...

  15. EST Table: FS895588 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS895588 E_FL_ftes_18N10_R_0 10/09/28 46 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...46 %/151 aa gnl|Amel|GB14856-PA 10/09/10 46 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS891321 ftes ...

  16. EST Table: FS880548 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS880548 E_FL_ftes_18N10_F_0 10/09/28 45 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...45 %/151 aa gnl|Amel|GB14856-PA 10/09/10 45 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS906679 ftes ...

  17. EST Table: FS920143 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS920143 E_FL_fufe_49H24_F_0 11/12/09 GO hit GO:0005874(microtubule)|GO:0007021(tub...:AGAP002130 10/09/10 59 %/109 aa gnl|Amel|GB17804-PA 10/09/10 60 %/109 aa gi|91091982|ref|XP_969241.1| PREDICTED: similar to AGAP002130-PA [Tribolium castaneum] FS920143 fufe ...

  18. EST Table: FS885453 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS885453 E_FL_ftes_33C19_F_0 10/09/28 97 %/223 aa ref|NP_001036831.1| saposin-relat...a gnl|Amel|GB16561-PA 10/09/10 40 %/239 aa gi|91077504|ref|XP_966852.1| PREDICTED: similar to saposin isoform 1 [Tribolium castaneum] FS791050 ftes ...

  19. EST Table: FS798702 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS798702 E_FL_ffbm_28C11_F_0 10/09/28 89 %/278 aa ref|NP_001036831.1| saposin-relat...a gnl|Amel|GB16561-PA 10/09/10 52 %/117 aa gi|91077504|ref|XP_966852.1| PREDICTED: similar to saposin isoform 1 [Tribolium castaneum] FS791050 ffbm ...

  20. EST Table: FS795138 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS795138 E_FL_ffbm_17H02_F_0 10/09/28 92 %/267 aa ref|NP_001036831.1| saposin-relat...a gnl|Amel|GB16561-PA 10/09/10 55 %/106 aa gi|91077504|ref|XP_966852.1| PREDICTED: similar to saposin isoform 1 [Tribolium castaneum] FS791050 ffbm ...

  1. In vitro effects of PCDDs/Fs on NK-like cell activity of Eisenia andrei earthworms

    Directory of Open Access Journals (Sweden)

    Hayet Belmeskine

    2012-02-01

    Full Text Available In this study, we assessed in vitro the effects of PCDD/Fs on the NK-like cell activity in Eisenia andrei earthworms using flow cytometry for analysis. NK-like coelomocytes isolated from E. andrei and used as effectors were exposed to various concentrations of PCDDs/Fs mixture, C1 (6.25x10-3 ng 2378- TCDD/mL, C2 (12.5x10-3 ng 2378-TCDD/mL and C3 (25x10-3 ng 2378-TCDD/mL, before adding them to human tumoral cells (K562 used as targets. We evaluated the percentage of targets lysed by Nk-like cells. The results showed a significant stimulation of the NKlike activity at C3 when PCDD/Fs were not removed from effectors before contact with targets, while no effects were noted when the effectors were washed (PCDD/Fs removed or fixed. Assessment of the viability of the targets (K562, exposed alone and separately from effectors, to the three concentrations of PCDD/Fs, C1, C2 and C3, showed that all these concentrations were cytotoxic for K562. Results suggest that PCDD/Fs concentrations tested in this assay may be considered too low to induce suppressive effects on the immune function such as the NK-like activity in E. andrei earthworms.

  2. EST Table: FS875608 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS875608 E_FL_ftes_04F20_F_0 10/09/28 45 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...45 %/151 aa gnl|Amel|GB14856-PA 10/09/10 45 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS906679 ftes ...

  3. EST Table: FS891805 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS891805 E_FL_ftes_04F20_R_0 10/09/28 46 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...46 %/151 aa gnl|Amel|GB14856-PA 10/09/10 46 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS891321 ftes ...

  4. EST Table: FS874950 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS874950 E_FL_ftes_02G24_F_0 10/09/28 45 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...45 %/151 aa gnl|Amel|GB14856-PA 10/09/10 45 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS906679 ftes ...

  5. EST Table: FS862828 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS862828 E_FL_fner_20A08_R_0 10/09/28 46 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...46 %/151 aa gnl|Amel|GB14856-PA 10/09/10 46 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS891321 fner ...

  6. EST Table: FS844168 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS844168 E_FL_fner_20A08_F_0 10/09/28 45 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...45 %/151 aa gnl|Amel|GB14856-PA 10/09/10 45 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS906679 fner ...

  7. EST Table: FS847583 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS847583 E_FL_fner_29M11_F_0 10/09/28 45 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...45 %/151 aa gnl|Amel|GB14856-PA 10/09/10 45 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS906679 fner ...

  8. EST Table: FS865993 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS865993 E_FL_fner_29M11_R_0 10/09/28 46 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...46 %/151 aa gnl|Amel|GB14856-PA 10/09/10 46 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS891321 fner ...

  9. EST Table: FS887803 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS887803 E_FL_ftes_40G04_F_0 10/09/28 35 %/122 aa ref|XP_967620.1| PREDICTED: similar to anopheles stephen... %/149 aa gnl|Amel|GB19565-PA 10/09/10 35 %/122 aa gi|91093471|ref|XP_967620.1| PREDICTED: similar to anopheles stephensi ubiquitin, putative [Tribolium castaneum] FS914988 ftes ...

  10. EST Table: FS900811 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS900811 E_FL_ftes_40G04_R_0 10/09/28 35 %/117 aa ref|XP_967620.1| PREDICTED: similar to anopheles stephen... %/144 aa gnl|Amel|GB19565-PA 10/09/10 35 %/117 aa gi|91093471|ref|XP_967620.1| PREDICTED: similar to anopheles stephensi ubiquitin, putative [Tribolium castaneum] FS788262 ftes ...

  11. EST Table: FS915066 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS915066 E_FL_fufe_34C05_F_0 10/09/28 35 %/122 aa ref|XP_967620.1| PREDICTED: similar to anopheles stephen... %/149 aa gnl|Amel|GB19565-PA 10/09/10 35 %/122 aa gi|91093471|ref|XP_967620.1| PREDICTED: similar to anopheles stephensi ubiquitin, putative [Tribolium castaneum] FS914988 fufe ...

  12. EST Table: FS869999 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS869999 E_FL_fner_41G01_R_0 10/09/28 90 %/258 aa ref|NP_001037132.1| ribosomal pro...6-PB 10/08/29 38 %/244 aa R151.3#CE00744#WBGene00004417#locus:rpl-6#Ribosomal protein ML16#status:Confirmed#UniProt:P4799

  13. EST Table: FS737308 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS737308 E_FL_bmmt_08H07_R_0 11/12/09 GO hit GO:0003678(DNA helicase activity)|GO:0...455:8982171:1|gene:AGAP010720 10/09/10 70 %/220 aa gnl|Amel|GB17337-PA 10/09/10 71 %/212 aa gi|189235245|ref...|XP_970366.2| PREDICTED: similar to pom1 [Tribolium castaneum] FS737308 bmmt ...

  14. (1S,3S,8R,9S,10R-9,10-Epoxy-3,7,7,10-tetramethyltricyclo[6.4.0.01,3]dodecane

    Directory of Open Access Journals (Sweden)

    Abdoullah Bimoussa

    2014-04-01

    Full Text Available The title compound, C16H26O, was synthesized by treating (1S,3S,8R-3,7,7,10-tetramethyltricyclo[6.4.0.01,3]dodec-9-ene with metachloroperbenzoic acid. The molecule is built up from two fused six- and seven-membered rings. The six-membered ring has a half-chair conformation, whereas the seven-membered ring displays a boat conformation. In the crystal, there are no significant intermolecular interactions present.

  15. RESAR-3S. Reference safety analysis report, volume 1

    International Nuclear Information System (INIS)

    1975-01-01

    The nuclear steam supply system consists of a Westinghouse pressurized water reactor and closed reactor coolant loops connected in parallel to the reactor vessel. Each loop contains a reactor coolant pump and a steam generator. Also described are an electrically heated pressurizer and certain auxiliary systems. The thermal output of the system is 3425 MW(t) and the thermal output of the core is 3411 MW(t). (FS)

  16. EST Table: FS771324 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS771324 E_FL_fcaL_21P07_F_0 10/09/28 46 %/146 aa ref|XP_973163.1| PREDICTED: similar to jump...45 %/146 aa gnl|Amel|GB14856-PA 10/09/10 46 %/146 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS906679 fcaL ...

  17. EST Table: FS787608 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS787608 E_FL_fcaL_21P07_R_0 10/09/28 46 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...46 %/151 aa gnl|Amel|GB14856-PA 10/09/10 46 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS891321 fcaL ...

  18. EST Table: FS803374 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS803374 E_FL_fmgV_12D12_F_0 10/09/28 45 %/149 aa ref|XP_973163.1| PREDICTED: similar to jump...46 %/150 aa gnl|Amel|GB14856-PA 10/09/10 45 %/149 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS906679 fmgV ...

  19. EST Table: FS822360 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS822360 E_FL_fmgV_12D12_R_0 10/09/28 46 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...46 %/151 aa gnl|Amel|GB14856-PA 10/09/10 46 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS891321 fmgV ...

  20. EST Table: FS928974 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS928974 E_FL_fwgP_23N08_F_0 10/09/28 45 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...45 %/151 aa gnl|Amel|GB14856-PA 10/09/10 45 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS906679 fwgP ...

  1. EST Table: FS923051 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS923051 E_FL_fwgP_06G17_F_0 10/09/28 45 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...45 %/151 aa gnl|Amel|GB14856-PA 10/09/10 45 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS906679 fwgP ...

  2. EST Table: FS934225 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS934225 E_FL_fwgP_39G18_F_0 10/09/28 34 %/122 aa ref|XP_967620.1| PREDICTED: similar to anopheles stephen... %/149 aa gnl|Amel|GB19565-PA 10/09/10 34 %/122 aa gi|91093471|ref|XP_967620.1| PREDICTED: similar to anopheles stephensi ubiquitin, putative [Tribolium castaneum] FS914988 fwgP ...

  3. Steady-state chlorophyll fluorescence (Fs) as a tool to monitor plant heat and drought stress

    Science.gov (United States)

    Cendrero Mateo, M.; Carmo-Silva, A.; Salvucci, M.; Moran, S. M.; Hernandez, M.

    2012-12-01

    Crop yield decreases when photosynthesis is limited by heat or drought conditions. Yet farmers do not monitor crop photosynthesis because it is difficult to measure at the field scale in real time. Steady-state chlorophyll fluorescence (Fs) can be used at the field level as an indirect measure of photosynthetic activity in both healthy and physiologically-perturbed vegetation. In addition, Fs can be measured by satellite-based sensors on a regular basis over large agricultural regions. In this study, plants of Camelina sativa grown under controlled conditions were subjected to heat and drought stress. Gas exchange and Fs were measured simultaneously with a portable photosynthesis system under light limiting and saturating conditions. Results showed that Fs was directly correlated with net CO2 assimilation (A) and inversely correlated with non-photochemical quenching (NPQ). Analysis of the relationship between Fs and Photosynthetically Active Radiation (PAR) revealed significant differences between control and stressed plants that could be used to track the status, resilience, and recovery of photochemical processes. In summary, the results provide evidence that Fs measurements, even without normalization, are an easy means to monitor changes in plant photosynthesis, and therefore, provide a rapid assessment of plant stress to guide farmers in resource applications. Figure1. Net CO2 assimilation rate (A) of Camelina sativa plants under control conditions and after heat stress exposure for 1 or 3 days (1d-HS and 3d-HS, respectively) (right) and control, drought and re-watering conditions (left). Conditions for infra-red gas analysis were: reference CO2 = 380 μmol mol-1, PPFD = 500 μmol m-2 s-1 and Tleaf set to 25°C (control, drought and re-water) or 35°C (HS). Different letters denote significant differences at the α=0.05 level. Values are means±SEM (n=10). Figure 2. Stable chlorophyll fluorescence (Fs) of Camelina sativa plants under control conditions and

  4. EST Table: FS750177 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS750177 E_ET_caL-_21J18_F_0 11/12/09 n.h 10/09/28 90 %/101 aa ref|NP_001036899.1| pro-corazon...in precursor [Bombyx mori] sp|Q86N75.1|CORZ_BOMMO RecName: Full=Pro-corazonin; Short=Crz; Short=B...CPRP; Flags: Precursor dbj|BAC66443.1| corazonin preprohormone [Bombyx mori] 10/09/08 n.h 10/08/28 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS750177 caL- ...

  5. EST Table: FS755944 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS755944 E_ET_caL-_21J18_R_0 11/12/09 n.h 10/09/28 91 %/101 aa ref|NP_001036899.1| pro-corazon...in precursor [Bombyx mori] sp|Q86N75.1|CORZ_BOMMO RecName: Full=Pro-corazonin; Short=Crz; Short=B...CPRP; Flags: Precursor dbj|BAC66443.1| corazonin preprohormone [Bombyx mori] 10/09/08 n.h 10/08/28 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS755944 caL- ...

  6. Plutonium-burn high temperature gas-cooled reactor for 3E+3S

    International Nuclear Information System (INIS)

    Okamoto, Koji

    2015-01-01

    The Nuclear Energy Development in Japan is facing a very difficult conditions after Fukushima-Daiichi NPP Accident. Nuclear Energy has strong advantages on 3E, i.e., Energy security, Economical efficiency and Environment. However, people does not believe the Safety 'S' of Nuclear Energy, now. The disadvantage of 'S' overrides the advantages of '3E'. In Nuclear Energy, 'S' is expanded into 3S, i.e., Safety, Security and Safeguards. Especially, the management of Plutonium inventory in Spent Fuel generated by the NPP operation is very important in the viewpoints of non-proliferation. The high-temperature gas cooled reactor (HTGR) is the solution of these disadvantages of '3S' in Nuclear Energy. The fuel of HTGR is composed by 1 mm spherical fuel particle, i.e., TRISO made by fuel, graphite and silicon-carbide. The silicon-carbide can confine the fission products in any conditions of fuel life cycle, i.e., during operation, accidents and disposal for 1 million years. The confinement of the radioactive materials can be confirmed by the TRISO. The HTGR core has strong negative feedback for temperature. So, the fission automatically stopped at the accidental conditions, such as loss of flow and LOCA. Also, the residual heat can be cooled by the radiation heat transfer to reactor vessel wall. The HTGR system usually has passive vessel wall cooling system. When the passive cooling system had been failed, the heat can be transferred to the land by heat conductions, and fuel does not reach the SiC broken temperature. The fission chain reaction has been stopped automatically by negative feedback, i.e., physics. The residual heat had been cooled automatically by radiation. The radioactive materials had been confined automatically by silicon-carbide. The HTGR is superior for 'S' safety. Plutonium can be burned by the HTGR. In the viewpoints of non-proliferation, the fuel should be made by YSZ-PuO 2 , stabilized buffer

  7. Experiment Operating Specification for the Semiscale MOD-2C feedwater and steam line break experiment series. Appendix S-FS-6 and 7

    International Nuclear Information System (INIS)

    Boucher, T.J.; Owca, W.A.

    1985-05-01

    This document is the Semiscale MOD-2C feedwater and steam line break experiment series Experiment Operating Specification Appendix for tests S-FS-6 and S-FS-7. Test S-FS-6 is the third test in the series and simulates a 100% break in a steam generator bottom feedwater line downstream of the check valve accompanied by compounding factors (such as check valve failure, loss-of-offsite power at SIS and SIS delayed until low steam generator pressure signal). The test is terminated after plant stabilization and recovery procedures including unaffected loop steam and feed, pressurizer heater operation, pressurizer auxiliary spray operation, and normal charging/letdown operation. Test S-FS-7 is the fourth test in the series and simulates a 14.3% break in a steam generator bottom feedwater line downstream of the check valve, accompanied by compounding factors. The test is terminated after plant stabilization procedures including unaffected loop steam and feed, pressurizer heater operation, and normal charging/letdown operation. The test was followed by an affected loop secondary refill after isolating the break. The Appendix contains information on the major fluid systems, initial experiment conditions, experiment boundary conditions, and sequence of experiment events. Also included is a discussion of the scaling criteria and philosophy used to develop the experiment initial and boundary conditions and system configuration

  8. EST Table: FS764450 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS764450 E_FL_fcaL_36N15_F_0 10/09/28 42 %/214 aa ref|XP_001945612.1| PREDICTED: similar to glucocerebro...608.1| PREDICTED: similar to putative lysosomal glucocerebrosidase [Tribolium castaneum] FS759318 fcaL ...

  9. Design of a 10-bit 100 MSamples/s BiCMOS D/A converter

    DEFF Research Database (Denmark)

    Jørgensen, Ivan Harald Holger; Tunheim, S. A.

    1995-01-01

    A 10-bit 100 MSamples/s current-steering D/A converter (DAC) has been designed and processed in a 0.8 μm BiCMOS process. The DAC is intended for applications using direct digital synthesis, and focus has been set on achieving a high spurious free dynamic range (SFDR). The main part of the DAC...... current cell to steer the current. At a generated frequency of fg≈0.3·fs (fs=100 MSamples/s), the simulated SFDR is larger than 60 dB. The DAC operates at 5 V, and has a power consumption of approximately 650 mW. The area of the chip-core is 2.2 mm×2.2 mm. Furthermore a measure to estimate the SFDR...... for the DAC based on short term simulations is presented. This measure seems to correspond very well with SFDR for long term simulations...

  10. EST Table: FS933547 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS933547 E_FL_fwgP_37G10_F_0 10/09/28 56 %/205 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fwgP ...

  11. SeaWiFS technical report series. Volume 32: Level-3 SeaWiFS data products. Spatial and temporal binning algorithms

    Science.gov (United States)

    Hooker, Stanford B. (Editor); Firestone, Elaine R. (Editor); Acker, James G. (Editor); Campbell, Janet W.; Blaisdell, John M.; Darzi, Michael

    1995-01-01

    The level-3 data products from the Sea-viewing Wide Field-of-view Sensor (SeaWiFS) are statistical data sets derived from level-2 data. Each data set will be based on a fixed global grid of equal-area bins that are approximately 9 x 9 sq km. Statistics available for each bin include the sum and sum of squares of the natural logarithm of derived level-2 geophysical variables where sums are accumulated over a binning period. Operationally, products with binning periods of 1 day, 8 days, 1 month, and 1 year will be produced and archived. From these accumulated values and for each bin, estimates of the mean, standard deviation, median, and mode may be derived for each geophysical variable. This report contains two major parts: the first (Section 2) is intended as a users' guide for level-3 SeaWiFS data products. It contains an overview of level-0 to level-3 data processing, a discussion of important statistical considerations when using level-3 data, and details of how to use the level-3 data. The second part (Section 3) presents a comparative statistical study of several binning algorithms based on CZCS and moored fluorometer data. The operational binning algorithms were selected based on the results of this study.

  12. Directed Acceleration of Electrons from a Solid Surface by Sub-10-fs Laser Pulses

    International Nuclear Information System (INIS)

    Brandl, F.; Hidding, B.; Osterholz, J.; Hemmers, D.; Pretzler, G.; Karmakar, A.; Pukhov, A.

    2009-01-01

    Electrons have been accelerated from solid target surfaces by sub-10-fs laser pulses of 120 μJ energy which were focused to an intensity of 2x10 16 W/cm 2 . The electrons have a narrow angular distribution, and their observed energies exceed 150 keV. We show that these energies are not to be attributed to collective plasma effects but are mainly gained directly via repeated acceleration in the transient field pattern created by incident and reflected laser, alternating with phase-shift-generating scattering events in the solid.

  13. EST Table: FS773973 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS773973 E_FL_fcaL_03D22_R_0 11/12/09 GO hit GO:0004872(receptor activity)|GO:00054...n#status:Confirmed#UniProt:Q27874#protein_id:CAA84 677.1 10/09/10 30 %/244 aa AGAP000815-PA Protein|X:149373...2 aa gi|189241337|ref|XP_969214.2| PREDICTED: similar to integrin beta subunit (AGAP000815-PA) [Tribolium castaneum] FS773973 fcaL ...

  14. EST Table: FS732173 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS732173 E_FL_bmmt_25M21_F_0 10/09/28 70 %/116 aa ref|XP_002425199.1| conserved hyp...0 70 %/116 aa gi|91092740|ref|XP_973214.1| PREDICTED: similar to family with sequence similarity 108, member B1 [Tribolium castaneum] FS796084 bmmt ...

  15. Analyses of hypothetical nuclear criticality excursions in 10- and 20-MW freezer/sublimer vessels

    International Nuclear Information System (INIS)

    Haught, C.F.; Jordan, W.C.; Basoglu, B.; Dodds, H.L.; Wilkinson, A.D.

    1995-01-01

    A theoretical model is used to predict the consequences of a postulated hypothetical nuclear criticality excursion in a freezer/sublimer (F/S). Previous work has shown that an intrusion of water into a F/S may result in a critical configuration. A first attempt is made to model the neutronic and thermal-hydraulic phenomena occurring during a criticality excursion involving both uranium hexafluoride (UF 6 ) and uranyl fluoride (UO 2 F 2 ) solution, which is present in the F/S during upset conditions. The model employs point neutronics coupled with simple thermal hydraulics. Reactivity feedback from changes in the properties of the system are included in the model. The excursion is studied in a 10-MW F/S with an initial load of 3,500 kg of 5% weight enriched UF 6 and in a 20-MW F/S with an initial load of 6,800 kg of 2% weight enriched UF 6 . The magnitude of the fission release determined in this work is 5.93 x 10 18 fissions in the 10-MW F/S and 4.21 x 10 18 fissions in the 20-MW F/S. In order to demonstrate the reliability of the techniques used in this work, a limited validation study was conducted by comparing the fission release and peak fission rate determined by this work with experimental results for a limited number of experiments. The agreement between calculations and experiments in the validation study is considered to be satisfactory. The calculational results for the hypothetical accidents in the two F/S vessels appear reasonable

  16. Wet storage of nuclear spent fuel from nuclear research reactor WWR-S

    International Nuclear Information System (INIS)

    Dragolici, A. C; Zorliu, A.; Petran, C.; Mincu, I.

    2001-01-01

    Nuclear research reactor WWR-S of IFIN-HH was commissioned on 29 July 1957 and shut down on December 1997. Now it is in Conservation State. During 40 years , the reactor was operated about 150,000 hours at variable power level ranging within 5 W and 3500 kW, and producing a total power of 9,510 MWday. After 20 years of operation a large number of spent fuel elements became available for storage exceeding the stocking capacity of the small cooling pond near reactor. Therefore, in 1980 the nuclear spent fuel repository was commissioned that contains at present all the fuel elements burnt in the reactor during years, minus 51 S-36 fuel assemblies which are conserved in the cooling pond. This repository contains 4 identical ponds, each of them having the storage capacity of 60 fuel assemblies. Every pond having the outer sizes of 2,750 mm (length) x 900 mm (breadth) x 5,700 mm (depth), is made from a special aluminum alloy (AlMg 3 ), with the walls thickness of 10 mm and bottom thickness of 15 mm. Pond's lids are made of cast iron having the thickness of 500 mm; they provide only the biological protection for the maintenance personnel. A 1.5 m concrete layer ensures the biological protection of the ponds. Over the fuel elements in every pond a 4.5 m water layer is provided, playing the role of biological protection and coolant. Inside the ponds exists an aluminum rack, which contains 60 locations for fuel storage. The spacing between these locations was determined from considerations of criticality and it is was the same with that of the cooling pond near the reactor. To have supplementary protection in the case of an accident which can destroy the entire rack and put together all the fuel elements thus forming critical mass, cadmium plates were placed on the ponds bottom for a better neutron absorption. Exploitation of cooling pond near the WWR-S reactor which has the identical structure with that of nuclear spent fuel repository, demonstrate the reliability and

  17. Feasibility study on commercialized fast reactor cycle systems. Phase II final report

    International Nuclear Information System (INIS)

    Ieda, Yoshiaki; Uchikawa, Sadao; Okubo, Tsutomu; Ono, Kiyoshi; Kato, Atsushi; Kurisaka, Kenichi; Sakamoto, Yoshihiko; Sato, Kazujiro; Sato, Koji; Chikazawa, Yoshitaka; Nakai, Ryodai; Nakabayashi, Hiroki; Nakamura, Hirofumi; Namekawa, Takashi; Niwa, Hajime; Nomura, Kazunori; Hayashi, Hideyuki; Hayafune, Hiroki; Hirao, Kazunori; Mizuno, Tomoyasu; Muramatsu, Toshiharu; Ando, Masato; Ono, Katsumi; Ogata, Takanari; Kubo, Shigenobu; Kotake, Shoji; Sagayama, Yutaka; Takakuma, Katsuyuki; Tanaka, Toshihiko; Namba, Takashi; Fujii, Sumio; Muramatsu, Kazuyoshi

    2006-06-01

    A joint project team of Japan Atomic Energy Agency and the Japan Atomic Power Company (as the representative of the electric utilities) started the feasibility study on commercialized fast reactor cycle systems (F/S) in July 1999 in cooperation with Central Research Institute of Electric Power Industry and vendors. On the major premise of safety assurance, F/S aims to present an appropriate picture of commercialization of fast reactor (FR) cycle system which has economic competitiveness with light water reactor cycle systems and other electricity base load systems, and to establish FR cycle technologies for the future major energy supply. In the period from Japanese fiscal year (JFY) 1999 to 2000, the phase-I of F/S was carried out to screen our representative FR, reprocessing and fuel fabrication technologies. In the phase-II (JFY 2001-2005), the design study of FR cycle concepts, the development of significant technologies necessary for the feasibility evaluation, and the confirmation of key technical issues were performed to clarify the promising candidate concepts toward the commercialization. In this final phase-II report clarified the most promising concept, the R and D plan until around 2015, and the key issues for the commercialization. Based on the comprehensive evaluation in F/S, the combination of the sodium-cooled FR with MOX fuel core, the advanced-aqueous reprocessing process and the simplified-pelletizing fuel fabrication process was recommended as the mainline choice for the most promising concept. The concept exceeds in technical advancement, and the conformity to the development targets was higher compared with that of the others. Alternative technologies are prepared to be decrease the development risk of innovative technologies in the mainline choice. (author)

  18. Comparison of SeaWiFS measurements of the Moon with the U.S. Geological Survey lunar model.

    Science.gov (United States)

    Barnes, Robert A; Eplee, Robert E; Patt, Frederick S; Kieffer, Hugh H; Stone, Thomas C; Meister, Gerhard; Butler, James J; McClain, Charles R

    2004-11-01

    The Sea-Viewing Wide-Field-of-View Sensor (SeaWiFS) has made monthly observations of the Moon since 1997. Using 66 monthly measurements, the SeaWiFS calibration team has developed a correction for the instrument's on-orbit response changes. Concurrently, a lunar irradiance model has been developed by the U.S. Geological Survey (USGS) from extensive Earth-based observations of the Moon. The lunar irradiances measured by SeaWiFS are compared with the USGS model. The comparison shows essentially identical response histories for SeaWiFS, with differences from the model of less than 0.05% per thousand days in the long-term trends. From the SeaWiFS experience we have learned that it is important to view the entire lunar image at a constant phase angle from measurement to measurement and to understand, as best as possible, the size of each lunar image. However, a constant phase angle is not required for using the USGS model. With a long-term satellite lunar data set it is possible to determine instrument changes at a quality level approximating that from the USGS lunar model. However, early in a mission, when the dependence on factors such as phase and libration cannot be adequately determined from satellite measurements alone, the USGS model is critical to an understanding of trends in instruments that use the Moon for calibration. This is the case for SeaWiFS.

  19. Remedial Investigation/Feasibility Study (RI/FS) process, elements and techniques guidance

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-01

    This manual provides detailed guidance on Remedial Investigation/Feasibility Studies (RI/FSs) conducted pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) at Department of Energy (DOE) facilities. The purpose of the RI/FS, to assess the risk posed by a hazardous waste site and to determine the best way to reduce that risk, and its structure (site characterization, risk assessment, screening and detailed analysis of alternatives, etc.) is defined in the National Oil and Hazardous Substances Pollution Contingency Plan (NCP) and further explained in the Environmental Protection Agency`s (EPA`s) Guidance for Conducting Remedial Investigations and Feasibility Studies Under CERCLA (Interim Final) 540/G-89/004, OSWER Directive 9355.3-01, October 1988. Though issued in 1988, the EPA guidance remains an excellent source of information on the conduct and structure of an RI/FS. This document makes use of supplemental RI/FS-related guidance that EPA has developed since its initial document was issued in 1988, incorporates practical lessons learned in more than 12 years of experience in CERCLA hazardous site remediation, and drawing on those lessons, introduces the Streamlined Approach For Environmental Restoration (SAFER), developed by DOE as a way to proceed quickly and efficiently through the RI/FS process at DOE facilities. Thus as its title implies, this guidance is intended to describe in detail the process and component elements of an RI/FS, as well as techniques to manage the RI/FS effectively.

  20. Infrared Observations of FS CMa Stars

    Science.gov (United States)

    Sitko, Michael L.; Russell, R. W.; Lynch, D. K.; Grady, C. A.; Hammel, H. B.; Beerman, L. C.; Day, A. N.; Huelsman, D.; Rudy, R. J.; Brafford, S. M.; Halbedel, E. M.

    2009-01-01

    A subset of non-supergiant B[e] stars has recently been recognized as forming a fairly unique class of objects with very strong emission lines, infrared excesses, and locations not associated with star formation. The exact evolutionary state of these stars, named for the prototype FS CMa, is uncertain, and they have often been classified as isolated Herbig AeBe stars. We present infrared observations of two of these stars, HD 45677 (FS CMa), HD 50138 (MWC 158), and the candidate FS CMa star HD 190073 (V1295 Aql) that span over a decade in time. All three exhibit an emission band at 10 microns due to amorphous silicates, confirming that much (if not all) of the infrared excess is due to dust. HD 50138 is found to exhibit 20% variability between 3-13 microns that resembles that found in pre-main sequence systems (HD 163296 and HD 31648). HD 45677, despite large changes at visual wavelengths, has remained relatively stable in the infrared. To date, no significant changes have been observed in HD 190073. This work is supported in part by NASA Origins of Solar Systems grant NAG5-9475, NASA Astrophysics Data Program contract NNH05CD30C, and the Independent Research and Development program at The Aerospace Corporation.

  1. SeaWiFS Deep Blue Aerosol Optical Thickness Monthly Level 3 Climatology Data Gridded at 0.5 Degrees V004

    Data.gov (United States)

    National Aeronautics and Space Administration — The SeaWiFS Deep Blue Level 3 Monthly Climatology Product contains monthly global climatology gridded (0.5 x 0.5 deg) data derived from SeaWiFS Deep Blue Level 3...

  2. Study of the RP-10 reactor neutron beam applied to the neutron radiography

    International Nuclear Information System (INIS)

    Zegarra, Manuel; Lopez, Alcides

    2013-01-01

    We have studied the RP-10 reactor radial neutron beam No. 3, which is used for neutron radiographies, by comparing radiograph's with and without the inner duct, and neutron flux determination with in flakes along the external duct, being the presence of photons creating signals at comparable levels of neutron effects, which reduce the quality of the analysis, values around 10 6 and 10 4 n/cm 2 s for thermal and epithermal flux were obtained respectively. It is recommended evaluate the design of the internal duct which presents strong photon emission. (authors).

  3. SeaWiFS_L3b_SNSP_RRS

    Data.gov (United States)

    National Aeronautics and Space Administration — The SeaWiFS instrument was launched by Orbital Sciences Corporation on the OrbView-2 (a.k.a. SeaStar) satellite in August 1997, and collected data from September...

  4. SeaWiFS_L3b_CU_CHL

    Data.gov (United States)

    National Aeronautics and Space Administration — The SeaWiFS instrument was launched by Orbital Sciences Corporation on the OrbView-2 (a.k.a. SeaStar) satellite in August 1997, and collected data from September...

  5. SeaWiFS_L3b_SNWI_CHL

    Data.gov (United States)

    National Aeronautics and Space Administration — The SeaWiFS instrument was launched by Orbital Sciences Corporation on the OrbView-2 (a.k.a. SeaStar) satellite in August 1997, and collected data from September...

  6. EST Table: FS730803 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS730803 E_FL_bmmt_19O18_F_0 10/09/28 54 %/206 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 bmmt ...

  7. EST Table: FS918214 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS918214 E_FL_fufe_43K22_F_0 10/09/28 53 %/199 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fufe ...

  8. Bioremediation of polychlorinated-p-dioxins/dibenzofurans contaminated soil using simulated compost-amended landfill reactors under hypoxic conditions

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Wei-Yu; Wu, Jer-Horng, E-mail: enewujh@mail.ncku.edu.tw; Lin, Shih-Chiang; Chang, Juu-En

    2016-07-15

    Highlights: • We developed a new hypoxic reactor system for remediating PCDD/Fs. • We demonstrated effects of compost on the degradation of PCDD/Fs. • We uncovered microbial compositions and dynamics during the degradation of PCDD/Fs. - Abstract: Compost-amended landfill reactors were developed to reduce polychlorinated-p-dioxins and dibenzofurans (PCDD/Fs) in contaminated soils. By periodically recirculating leachate and suppling oxygen, the online monitoring of the oxidation reduction potential confirmed that the reactors were maintained under hypoxic conditions, with redox levels constantly fluctuating between −400 and +80 mV. The subsequent reactor operation demonstrated that PCDD/F degradation in soil could be facilitated by amending compost originating from the cow manure and waste sludge and that the degradation might be affected by the availability of easily degradable substrates in the soil and compost. The pyrosequencing analysis of V4/V5 regions of bacterial 16S rRNA genes suggested that species richness of the soil microbial community was increased by a factor of 1.37–1.61. Although the bacterial community varied with the compost origin and changed markedly during reactor operation, it was dominated by Alphaproteobacteria, Gammaproteobacteria, Actinobacteria, and Firmicutes. The aerotolerant anaerobic Sedimentibacter and Propionibacterium spp., and the uncultured Chloroflexi group could be temporarily induced to a high abundance by amending the cow manure compost; the bacterial growths were associated with the rapid degradation of PCDD/Fs. Overall, the novel bioremediation method for PCDD/F-contaminated soils using hypoxic conditions was effective, simple, energy saving, and thus easily practicable.

  9. Bioremediation of polychlorinated-p-dioxins/dibenzofurans contaminated soil using simulated compost-amended landfill reactors under hypoxic conditions

    International Nuclear Information System (INIS)

    Chen, Wei-Yu; Wu, Jer-Horng; Lin, Shih-Chiang; Chang, Juu-En

    2016-01-01

    Highlights: • We developed a new hypoxic reactor system for remediating PCDD/Fs. • We demonstrated effects of compost on the degradation of PCDD/Fs. • We uncovered microbial compositions and dynamics during the degradation of PCDD/Fs. - Abstract: Compost-amended landfill reactors were developed to reduce polychlorinated-p-dioxins and dibenzofurans (PCDD/Fs) in contaminated soils. By periodically recirculating leachate and suppling oxygen, the online monitoring of the oxidation reduction potential confirmed that the reactors were maintained under hypoxic conditions, with redox levels constantly fluctuating between −400 and +80 mV. The subsequent reactor operation demonstrated that PCDD/F degradation in soil could be facilitated by amending compost originating from the cow manure and waste sludge and that the degradation might be affected by the availability of easily degradable substrates in the soil and compost. The pyrosequencing analysis of V4/V5 regions of bacterial 16S rRNA genes suggested that species richness of the soil microbial community was increased by a factor of 1.37–1.61. Although the bacterial community varied with the compost origin and changed markedly during reactor operation, it was dominated by Alphaproteobacteria, Gammaproteobacteria, Actinobacteria, and Firmicutes. The aerotolerant anaerobic Sedimentibacter and Propionibacterium spp., and the uncultured Chloroflexi group could be temporarily induced to a high abundance by amending the cow manure compost; the bacterial growths were associated with the rapid degradation of PCDD/Fs. Overall, the novel bioremediation method for PCDD/F-contaminated soils using hypoxic conditions was effective, simple, energy saving, and thus easily practicable.

  10. EST Table: FS926804 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS926804 E_FL_fwgP_17H18_F_0 10/09/28 58 %/249 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fwgP ...

  11. EST Table: FS800709 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS800709 E_FL_fmgV_04M06_F_0 10/09/28 57 %/262 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fmgV ...

  12. EST Table: FS807612 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS807612 E_FL_fmgV_24A09_F_0 10/09/28 57 %/266 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fmgV ...

  13. EST Table: FS806480 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS806480 E_FL_fmgV_20N06_F_0 10/09/28 57 %/259 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fmgV ...

  14. EST Table: FS804646 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS804646 E_FL_fmgV_15M02_F_0 10/09/28 54 %/215 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fmgV ...

  15. EST Table: FS804486 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS804486 E_FL_fmgV_15E24_F_0 10/09/28 53 %/199 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fmgV ...

  16. EST Table: FS921913 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS921913 E_FL_fwgP_03B17_F_0 10/09/28 54 %/215 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fwgP ...

  17. EST Table: FS810510 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS810510 E_FL_fmgV_32C08_F_0 10/09/28 57 %/259 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fmgV ...

  18. EST Table: FS937969 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS937969 E_FL_fwgP_50K04_F_0 10/09/28 56 %/264 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fwgP ...

  19. EST Table: FS822271 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS822271 E_FL_fmgV_11P16_R_0 11/12/09 n.h 10/09/28 75 %/112 aa ref|XP_001656149.1| fetal alzheimer... antigen, falz [Aedes aegypti] gb|EAT35210.1| fetal alzheimer antigen, falz [Aedes aegypti] 1...8 %/115 aa gi|189240808|ref|XP_001811424.1| PREDICTED: similar to fetal alzheimer antigen, falz [Tribolium castaneum] FS822271 fmgV ...

  20. InterProScan Result: FS848106 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS848106 FS848106_3_ORF3 48EA3AE107CE2860 PIR PIRSF017267 Sulfiredoxin 3.9e-13 T IPR016692 Sulfire...doxin Molecular Function: sulfiredoxin activity (GO:0032542)|Biological Process: oxidation reduction (GO:0055114) ...

  1. InterProScan Result: FS888414 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS888414 FS888414_1_ORF2 7BD3608BC4DF6C01 PRINTS PR01186 INTEGRINB 7.4e-10 T IPR015812 Integri...0)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  2. CFX-10 and RELAP5-3D simulations of coolant mixing phenomena in RPV of VVER-1000 reactors

    International Nuclear Information System (INIS)

    Terzuoli, F.; Moretti, F.; Melideo, D.; D'Auria, F.; Shkarupa, O.

    2006-01-01

    The present paper deals with numerical analyses of coolant mixing in the reactor pressure vessel of a VVER-1000 reactor, performed with the ANSYS CFX-10 CFD code and with the RELAP5-3D system code. In particular, the attention focused on the 'swirl' effect that has been observed to take place in the downcomer of such kind of reactor, with the aim of assessing the capability of the codes to predict that effect, and to understand the reasons for its occurrence. The results have been compared against experimental data from V1000CT-2 Benchmark. (author)

  3. EST Table: FS819070 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available 1|gene:AGAP012772 10/09/10 47 %/123 aa gnl|Amel|GB30341-PA 10/09/10 47 %/123 aa gi|91086723|ref|XP_970869.1|... PREDICTED: similar to fear-of-intimacy CG6817-PA [Tribolium castaneum] FS825450 fmgV ...

  4. SeaWiFS

    Data.gov (United States)

    Washington University St Louis — SEAWiFS_US is a high resolution (1km) satellite dataset derived from the eight wavelength SEAWiFS sensor. The dataset also includes the aerosol reflectance over the...

  5. InterProScan Result: FS873218 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS873218 FS873218_6_ORF2 0A64BA7E960F39C4 PANTHER PTHR18958:SF308 gb def: Mus musculus 10 days neonate cereb...ellum cDNA, RIKEN full-length enriched library 7.7e-09 T IPR020683 unintegrated ...

  6. Licensing experience of the HTR-10 test reactor

    International Nuclear Information System (INIS)

    Sun, Y.; Xu, Y.

    1996-01-01

    A 10MW high temperature gas-cooled test reactor (HTR-10) is now being projected by the Institute of Nuclear Energy Technology within China's National High Technology Programme. The Construction Permit of HTR-10 was issued by the Chinese nuclear licensing authority around the end of 1994 after a period of about one year of safety review of the reactor design. HTR-10 is the first high temperature gas-cooled reactor (HTGR) to be constructed in China. The purpose of this test reactor project is to test and demonstrate the technology and safety features of the advanced modular high temperature reactor design. The reactor uses spherical fuel elements with coated fuel particles. The reactor unit and the steam generator unit are arranged in a ''side-by-side'' way. Maximum fuel temperature under the accident condition of a complete loss of coolant is limited to values much lower than the safety limit set for the fuel element. Since the philosophy of the technical and safety design of HTR-10 comes from the high temperature modular reactor design, the reactor is also called the Test Module. HTR-10 represents among others also a licensing challenge. On the one side, it is the first helium reactor in China, and there are less licensing experiences both for the regulator and for the designer. On the other side, the reactor design incorporates many advanced design features in the direction of passive or inherent safety, and it is presently a world-wide issue how to treat properly the passive or inherent safety design features in the licensing safety review. In this presentation, the licensing criteria of HTR-10 are discussed. The organization and activities of the safety review for the construction permit licensing are described. Some of the main safety issues in the licensing procedure are addressed. Among these are, for example, fuel element behaviour, source term, safety classification of systems and components, containment design. The licensing experiences of HTR-10 are of

  7. EST Table: FS849735 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available acetyltransferase [Periplaneta americana] 10/09/11 34 %/218 aa FBpp0169479|DmojGI20262-PA 10/08/29 n.h 10/09...FS849735 E_FL_fner_35N12_F_0 10/09/28 33 %/215 aa dbj|BAC87874.1| arylalkylamine N-

  8. Investigations related to a one-piece removal of the reactor block in the frame of the JRR-3 reconstruction program

    International Nuclear Information System (INIS)

    Onishi, N.; Kanenari, A.; Futamura, Y.; Sakurai, H.; Suzuki, S.; Nagase, T.; Iwatani, A.; Otsubo, F.

    1987-01-01

    In the Japan Atomic Energy Research Institute (JAERI), an outdated research reactor (Japan Research Reactor No.3; JRR-3) was removed to a storage facility between October 14th and November 7th, 1986. The removal of the 2250-ton reactor block (10 x 10 x 10 m) was performed as a part of a program to replace the JRR-3's core (10-MW thermal) with an upgraded research reactor core. The heavy water and fuel elements were taken out from the JRR-3 before removal work began. The reactor block was raised about 3.7 meters, using a 12-cubic meter steel frame and a center-hole jack system. The reactor block was then transported horizontally about 34 meters on steel rails, using four 100-ton jacks, to a storage facility. Finally, the reactor block was lowered 14 meters into the storage facility. After the reactor block was stored, a new 20-MW thermal, light-water moderated and cooled JRR-3 core will be built, with criticality targeted for 1989

  9. EST Table: FS725108 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS725108 E_FL_bmmt_03L12_F_0 10/09/28 58 %/105 aa gb|ACY09589.1| cytochrome oxidase subunit 1 [Tetracis cach...exiata] 10/09/03 low homology 10/08/28 low homology 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h AU001277 bmmt ...

  10. EST Table: FS731731 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS731731 E_FL_bmmt_24I23_F_0 10/09/28 44 %/191 aa ref|XP_001869607.1| monocarboxyla...10/09/03 39 %/191 aa FBpp0160203|DmojGI10986-PA 10/08/28 low homology 10/09/10 44 %/191 aa AGAP002587-PA Pro

  11. InterProScan Result: FS885591 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS885591 FS885591_3_ORF2 718F710ADBEB9510 SUPERFAMILY SSF51621 Phosphoenolpyruvate/pyruva...te domain 1.3e-13 T IPR015813 Pyruvate/Phosphoenolpyruvate kinase, catalytic core Molecular Function: catalytic activity (GO:0003824) ...

  12. Fat-suppressed three-dimensional fast spoiled gradient-recalled echo imaging: a modified FS 3D SPGR technique for assessment of patellofemoral joint chondromalacia.

    Science.gov (United States)

    Wang, S F; Cheng, H C; Chang, C Y

    1999-01-01

    Fast fat-suppressed (FS) three-dimensional (3D) spoiled gradient-recalled echo (SPGR) imaging of 64 articular cartilage regions in 16 patellofemoral joints was evaluated to assess its feasibility in diagnosing patellofemoral chondromalacia. It demonstrated good correlation with arthroscopic reports and took about half of the examination time that FS 3D SPGR did. This modified, faster technique has the potential to diagnose patellofemoral chondromalacia with shorter examination time than FS 3D SPGR did.

  13. InterProScan Result: FS860732 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS860732 FS860732_6_ORF1 0375CFA2D74CE0C2 PANTHER PTHR10082:SF12 INTEGRIN BETA-3 3....007160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  14. InterProScan Result: FS911973 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS911973 FS911973_2_ORF3 FBDFC7C1F8C27366 PANTHER PTHR11792 ARRESTIN 6.3e-12 T IPR000698 Arrestin Biological... Process: signal transduction (GO:0007165)|Biological Process: sensory perception (GO:0007600) ...

  15. EST Table: FS827794 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS827794 E_FL_fmgV_27G02_R_0 10/09/28 42 %/239 aa ref|XP_002092266.1| GE14094 [Dros...ophila yakuba] gb|EDW91978.1| GE14094 [Drosophila yakuba] 10/09/10 42 %/239 aa FBpp0259104|DyakGE14094-PA 10

  16. EST Table: FS920967 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS920967 E_FL_fufe_52E08_F_0 10/09/28 83 %/296 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/13 low homology 10/08/29 n.h 10/09

  17. EST Table: FS910029 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS910029 E_FL_fufe_19A04_F_0 10/09/28 88 %/296 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09

  18. EST Table: FS908976 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS908976 E_FL_fufe_15N15_F_0 10/09/28 88 %/289 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09

  19. EST Table: FS910254 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS910254 E_FL_fufe_19K18_F_0 10/09/28 87 %/274 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09

  20. EST Table: FS913950 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS913950 E_FL_fufe_30M22_F_0 10/09/28 87 %/272 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09

  1. EST Table: FS919738 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS919738 E_FL_fufe_48E09_F_0 10/09/28 87 %/288 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/13 low homology 10/08/29 n.h 10/09

  2. EST Table: FS758989 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS758989 E_FL_fcaL_09P10_F_0 10/09/28 34 %/195 aa ref|XP_001842174.1| sensitized chromosome inheritance... modifier 19 [Culex quinquefasciatus] gb|EDS39679.1| sensitized chromosome inheritance m

  3. EST Table: FS841713 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available ar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] 10/09/10 53 %/160 aa FBpp0120238|DanaGF170... similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fner ...

  4. Dosimetry aspects of the new Canadian MAPLE-X10 reactor

    International Nuclear Information System (INIS)

    Lidstone, R.F.; Wilkin, G.B.

    1994-01-01

    Atomic Energy of Canada Limited is building the 10-MW t MAPLE-X10 reactor facility as a dedicated producer of medical and industrial radioisotopes. Dosimetry aspects of the MAPLE-X10 nuclear design include the calculated thermal and fast neutron flux distributions throughout the reactor assembly and the rate of heat generation in reactor materials and components. Examples of the resolution of design issues are also presented, such as the use of fission counters and ion chambers to provide diverse methods of detecting neutron flux levels and the use of the difference between photon and neutron signals to guard against the effects of downgrading of the heavy-water reflector. Computer codes employed in the calculations include MCNP, ONEDANT, WIMS-AECL, and 3DDT

  5. Evaluation of PCDD/Fs emissions during ceramic production: a laboratory study.

    Science.gov (United States)

    Lu, Mang; Luo, Yi-Jing; Zhang, Zhong-Zhi; Xiao, Meng; Zhang, Min

    2012-08-30

    Because of the ubiquity of polychlorinated dibenzo-p-dioxins and dibenzofurans (PCDD/Fs) in kaolinitic clays, the ceramic industry is considered to be a potential source of PCDD/Fs. However, studies on the emission of PCDD/Fs from ceramic production are still very scarce. In this study, PCDD/Fs emissions during ceramic production were investigated in an electric laboratory batch kiln. The results showed that the PCDD/Fs were completely removed from the ceramic pieces after 30 min of firing at the peak temperature of 1200°C. Nevertheless, on the mass and international toxic equivalent basis, 27.5% and 46.2% of the total PCDD/Fs amount in the raw clay were released into the atmosphere during firing, respectively. These PCDD/Fs were emitted into the air before the temperature was elevated to a level high enough for their destruction. Dechlorination reactions generated a broad distribution within the PCDD/Fs congeners including a variety of non-2,3,7,8-substituted ones. The emission of PCDD/Fs was decreased to 16.3 wt.% of the total PCDD/Fs amount in the raw clay, when the initial kiln temperature was enhanced to 600°C. The emission of PCDD/Fs could be reduced significantly in the presence of a glaze coating on the ceramic test piece. These results indicated that ceramic production is an un-neglectable source of PCDD/Fs in the environment. Copyright © 2012 Elsevier B.V. All rights reserved.

  6. Strategy to support HTGR fuel for the 10 MW Indonesia’s experimental power reactor (RDE)

    International Nuclear Information System (INIS)

    Taswanda Taryo; Geni Rina Sunaryo; Ridwan; Meniek Rachmawati

    2018-01-01

    The Indonesia’s 10 MW experimental power reactor (RDE) is developed based on high temperature gas-cooled reactor (HTGR) and the program of the RDE was firstly introduced to the Agency for National Development Planning (BAPPENAS) at the beginning of 2014. The RDE program is expected to have positive impacts on community prosperity, self-reliance and sovereignty of Indonesia. The availability of RDE will be able to accelerate advanced nuclear power technology development and hence elevate Indonesia to be the nuclear champion in the ASEAN region. The RDE is expected to be operable in 2022/2023. In terms of fuel supply for the reactor, the first batch of RDE fuel will be inclusive in the RDE engineering, procurement and construction (RDE-EPC) contract for the assurance of the RDE reactor operation from 2023 to 2027. Consideration of RDE fuel plant construction is important as RDE can be the basis for the development of reactors of similar type with small-medium power(25 MWe–200/300 MWe), which are preferable for eastern part of Indonesia. To study the feasibility of the construction of RDE fuel plant, current state of the art of the R&D on HTGR fuel in some advanced countries such as European countries, the United States, South Africa and Japan will be discussed and overviewed to draw a conclusion about the prospective countries for supporting the fuel for long-term RDE operation. The strategy and road map for the preparation of the RDE fuel plant construction with the involvement of national stake holders have been developed. The best possible vendor country to support HTGR fuel for long-term operation is finally accomplished. In the end, this paper can be assigned as a reference for the planning and construction of HTGR RDE fuel fabrication plant in Indonesia. (author)

  7. InterProScan Result: FS895048 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS895048 FS895048_5_ORF1 A78EA11E5E964520 PRINTS PR00385 P450 4.5e-10 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  8. SeaWiFS_L3b_8D_POC

    Data.gov (United States)

    National Aeronautics and Space Administration — The SeaWiFS instrument was launched by Orbital Sciences Corporation on the OrbView-2 (a.k.a. SeaStar) satellite in August 1997, and collected data from September...

  9. PBDD/Fs in surface sediments from the East River, China.

    Science.gov (United States)

    Ren, M; Peng, P A; Chen, D Y; Chen, P; Zhou, L

    2009-09-01

    The contamination status of polybrominated dibenzo-p-dioxins and dibenzofurans (PBDD/Fs) was preliminarily investigated in surface sediments from the East River. The concentrations of eight 2,3,7,8-substituted tetra- to hexa- PBDD/Fs were found to be in the range of 0.32-110 (mean 13) pg g(-1) and the corresponding TEQ concentrations were 0.087-18 (mean 2) pg I-TEQ g(-1). All sediments were characterized by the dominant PBDFs. 2,3,4,7,8-PeBDF was the most important TEQ contributor, accounting for 47%-77% of the total I-TEQ of PBDD/Fs. PCDD/Fs contributed dominantly to the total TEQs of PCDD/Fs, PBDD/Fs and dioxin-like PCBs in most samples except of the sediment from the Shima River. The higher PBDD/F concentrations in the Shima River may be attributed to the use of BFRs in the electrical and electronics industries, which posed a potential risk of dioxins on ecological system.

  10. EST Table: FS840242 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available l|Amel|GB10584-PA 10/09/10 47 %/128 aa gi|91087383|ref|XP_975651.1| PREDICTED: similar to Glucosylceramidase precursor (Beta-glucocer...ebrosidase) (Acid beta-glucosidase) (D-glucosyl-N-acylsphingosine glucohydrolase) [Tribolium castaneum] FS796494 fner ...

  11. EST Table: FS736730 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS736730 E_FL_bmmt_06M14_R_0 10/09/28 100 %/193 aa ref|NP_001037510.1| elongation f... dbj|BAA02601.1| elongation factor 1 alpha [Bombyx mori] 10/09/03 95 %/193 aa FBpp0257399|DyakGE12389-PA 10/

  12. EST Table: FS747376 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available milar to xaa-pro dipeptidase pepd/pepq(e.coli) [Nasonia vitripennis] 10/09/08 58 %/234 aa FBpp0241989|DwilGK...AP004775 10/09/10 low homology 10/09/10 54 %/235 aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 caL- ...

  13. Removal of arsenic from water by Friedel's salt (FS: 3CaO·Al2O3·CaCl2·10H2O).

    Science.gov (United States)

    Zhang, Danni; Jia, Yongfeng; Ma, Jiayu; Li, Zhibao

    2011-11-15

    Low levels of arsenic can be effectively removed from water by adsorption onto various materials and searching for low-cost, high-efficiency new adsorbents has been a hot topic in recent years. In the present study, the performance of Friedel's salt (FS: 3CaO·Al(2)O(3)·CaCl(2)·10H(2)O), a layered double hydroxide (LDHs), as an adsorbent for arsenic removal from aqueous solution was investigated. Friedel's salt was synthesized at lower temperature (50°C) compared to traditional autoclave methods by reaction of calcium chloride with sodium aluminate. Kinetic study revealed that adsorption of arsenate by Friedel's salt was fast in the first 12h and equilibrium was achieved within 48 h. The adsorption kinetics are well described by second-order Lageren equation. The adsorption capacity of the synthesized sorbent for arsenate at pH 4 and 7 calculated from Langmuir adsorption isotherms was 11.85 and 7.80 mg/g, respectively. Phosphate and silicate markedly decreased the removal of arsenate, especially at higher pH, but sulfate was found to suppress arsenate adsorption at lower pH and the adverse effect was disappeared at pH ≥ 6. Common metal cations (Ca(2+), Mg(2+)) enhanced arsenate adsorption. The results suggest that Friedel's salt is a potential cost-effective adsorbent for arsenate removal in water treatment. Copyright © 2011 Elsevier B.V. All rights reserved.

  14. EST Table: FS839039 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS839039 E_FL_fner_05J12_F_0 10/09/28 57 %/212 aa gb|ADE18444.1| cytochrome c oxida...se subunit I [Bombyx mori] 10/09/10 50 %/212 aa FBpp0100176|mt:CoI-PA 10/08/29 39 %/207 aa MTCE.26#CE35350#W

  15. EST Table: FS920740 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS920740 E_FL_fufe_51G05_F_0 10/09/28 40 %/209 aa ref|XP_001867321.1| partner of drosha... [Culex quinquefasciatus] gb|EDS44779.1| partner of drosha [Culex quinquefasciatus] 10/09/13 39 %/204 aa

  16. EST Table: FS915741 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS915741 E_FL_fufe_36D23_F_0 10/09/28 88 %/287 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h NM_001105232 fufe ...

  17. EST Table: FS907852 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS907852 E_FL_fufe_12H06_F_0 10/09/28 92 %/258 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h NM_001105232 fufe ...

  18. EST Table: FS913382 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS913382 E_FL_fufe_29B08_F_0 10/09/28 87 %/287 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h NM_001105232 fufe ...

  19. EST Table: FS908536 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS908536 E_FL_fufe_14I01_F_0 10/09/28 93 %/263 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h NM_001105232 fufe ...

  20. Design study on sodium cooled large-scale reactor

    International Nuclear Information System (INIS)

    Murakami, Tsutomu; Hishida, Masahiko; Kisohara, Naoyuki

    2004-07-01

    In Phase 1 of the 'Feasibility Studies on Commercialized Fast Reactor Cycle Systems (F/S)', an advanced loop type reactor has been selected as a promising concept of sodium-cooled large-scale reactor, which has a possibility to fulfill the design requirements of the F/S. In Phase 2, design improvement for further cost reduction of establishment of the plant concept has been performed. This report summarizes the results of the design study on the sodium-cooled large-scale reactor performed in JFY2003, which is the third year of Phase 2. In the JFY2003 design study, critical subjects related to safety, structural integrity and thermal hydraulics which found in the last fiscal year has been examined and the plant concept has been modified. Furthermore, fundamental specifications of main systems and components have been set and economy has been evaluated. In addition, as the interim evaluation of the candidate concept of the FBR fuel cycle is to be conducted, cost effectiveness and achievability for the development goal were evaluated and the data of the three large-scale reactor candidate concepts were prepared. As a results of this study, the plant concept of the sodium-cooled large-scale reactor has been constructed, which has a prospect to satisfy the economic goal (construction cost: less than 200,000 yens/kWe, etc.) and has a prospect to solve the critical subjects. From now on, reflecting the results of elemental experiments, the preliminary conceptual design of this plant will be preceded toward the selection for narrowing down candidate concepts at the end of Phase 2. (author)

  1. InterProScan Result: FS917145 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available lular Component: endoplasmic reticulum (GO:0005783)|Cellular Component: integral to membrane (GO:0016021) ... ...FS917145 FS917145_2_ORF2 DB1A671B79D1A25B PFAM PF05208 ALG3 9e-110 T IPR007873 Glycosyltransferase, ALG3 Cel

  2. EST Table: FS846041 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS846041 E_FL_fner_25G13_F_0 10/09/28 50 %/132 aa ref|XP_001606590.1| PREDICTED: similar to glucocerebro...el|GB10584-PA 10/09/10 47 %/138 aa gi|91087383|ref|XP_975651.1| PREDICTED: similar to Glucosylceramidase precursor (Beta-glucocerebro

  3. The Flamanville 3 EPR reactor; Le reacteur EPR Flamanville 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    On April 10. 2007, the french government authorized EDF to create on the site of Flamanville ( La Manche) a nuclear base installation containing a pressurized water EPR type reactor. This nuclear reactor, conceived by AREVA NP and EDF, is the first copy of a generation susceptible to replace later, at least partly, the French nuclear reactors at present in operation.Within the framework of its mission of technical support of the Authority of Nuclear Safety ( A.S.N.), the I.R.S.N. widely contributed successively: to define the general objectives of safety assigned to this new generation of pressurized water nuclear reactors; to analyze the options of safety proposed by EDF for the EPR project; To deepen, upstream to the authorization of creation, the evaluation of the step of safety and the measures of conception retained by EDF that have to allow to respect the objectives of safety which were notified to it. (N.C.)

  4. Simulation for Remote Operation for REX10 Nuclear Reactor

    International Nuclear Information System (INIS)

    Lee, Sim Won; Kim, Dong Su; Na, Man Gyun; Lee, Yoon Joon; Lee, Yeon Gun; Park, Goon Cherl

    2010-01-01

    The newly designed REX10 (Regional Energy Reactor, 10MWth) is an environmentally-friendly and stable small nuclear reactor for a small-scale reactor based Multi-purpose regional energy system. The REX10 has been developed to maintain system safety in order to be placed in densely populated region, island, etc. In addition, it is significantly hard to recruit many operation and maintenance personnel for small power reactors differently from usual commercial reactors because of its remote location and of economic reasons. In order to overcome these constraints, to decrease the operation cost by reducing operation and maintenance personnel, and to increase plant reliability through autonomous plant control, it is needed to design the control system of the small power reactors and to establish its unmanned remote operation system. In this study, the REX10 reactor core thermal power controller is designed by using a REX10 code analyzer. The remote control facility through man-machine interface (MMI) design and interface between programming languages was established and it was used to verify remote operation of REX10

  5. EST Table: FS908806 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS908806 E_FL_fufe_15F06_F_0 10/09/28 64 %/229 aa ref|XP_974421.1| PREDICTED: similar to synoviolin.../09/10 58 %/222 aa gnl|Amel|GB14313-PA 10/09/10 64 %/229 aa gi|91087035|ref|XP_974421.1| PREDICTED: similar to synoviolin [Tribolium castaneum] DC547331 fufe ...

  6. EST Table: FS733278 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS733278 E_FL_bmmt_20O16_F_0 10/09/28 77 %/113 aa ref|XP_974421.1| PREDICTED: similar to synoviolin.../09/10 70 %/106 aa gnl|Amel|GB14313-PA 10/09/10 77 %/113 aa gi|91087035|ref|XP_974421.1| PREDICTED: similar to synoviolin [Tribolium castaneum] DC547331 bmmt ...

  7. Evaluation of the HTR-10 Reactor as a Benchmark for Physics Code QA

    International Nuclear Information System (INIS)

    William K. Terry; Soon Sam Kim; Leland M. Montierth; Joshua J. Cogliati; Abderrafi M. Ougouag

    2006-01-01

    The HTR-10 is a small (10 MWt) pebble-bed research reactor intended to develop pebble-bed reactor (PBR) technology in China. It will be used to test and develop fuel, verify PBR safety features, demonstrate combined electricity production and co-generation of heat, and provide experience in PBR design, operation, and construction. As the only currently operating PBR in the world, the HTR-10 can provide data of great interest to everyone involved in PBR technology. In particular, if it yields data of sufficient quality, it can be used as a benchmark for assessing the accuracy of computer codes proposed for use in PBR analysis. This paper summarizes the evaluation for the International Reactor Physics Experiment Evaluation Project (IRPhEP) of data obtained in measurements of the HTR-10's initial criticality experiment for use as benchmarks for reactor physics codes

  8. InterProScan Result: FS933294 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS933294 FS933294_3_ORF2 4539D97811267FB7 PFAM PF04695 Pex14_N NA ? IPR006785 unintegrated Cellular... Component: peroxisome (GO:0005777)|Cellular Component: membrane (GO:0016020) ...

  9. EST Table: FS813939 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS813939 E_FL_fmgV_41L05_F_0 10/09/28 65 %/121 aa ref|NP_001136225.1| hypothetical ...protein LOC100216500 [Bombyx mori] gb|ACJ66918.1| hypothetical protein 39 [Bombyx mori] 10/09/09 n.h 10/08/29 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h AU001277 fmgV ...

  10. MAPLE-X10 reactor digital control system

    International Nuclear Information System (INIS)

    Deverno, M.T.; Hinds, H.W.

    1991-10-01

    The MAPLE-X10 reactor, currently under construction at the Chalk River Laboratories of Atomic Energy of Canada Limited, is a 10 MW t , pool-type, light-water reactor. It will be used for radioisotope production and silicon neutron transmutation doping. The reactor is controlled by a Digital Control System (DCS) and protected against abnormal process events by two independent safety systems. The DCS is an integrated control system used to regulate the reactor power and process systems. The safety philosophy for the control system is to minimize unsafe events arising from system failures and operational errors. this is achieved through redundancy, fail-safe design, automatic fault detection, and the selection of highly reliable components. The DCS provides both computer-controlled reactor regulation from the shutdown state to full power and automated reactor shutdown if safe limits are exceeded or critical sensors malfunction. The use of commercially available hardware with enhanced quality assurance makes the system cost effective while providing a high degree of reliability

  11. EST Table: FS796464 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available ar to putative lysosomal glucocerebrosidase [Tribolium castaneum] 10/09/09 32 %/334 aa FBpp0237202|DvirGJ227...milar to putative lysosomal glucocerebrosidase [Tribolium castaneum] FS796494 ffbm ...

  12. EST Table: FS928371 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS928371 E_FL_fwgP_22B11_F_0 10/09/28 87 %/119 aa ref|XP_975463.1| PREDICTED: similar to rasputin...066-PA 10/09/10 87 %/119 aa gi|91076984|ref|XP_975463.1| PREDICTED: similar to rasputin CG9412-PB [Tribolium castaneum] CK541017 fwgP ...

  13. InterProScan Result: FS775902 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS775902 FS775902_6_ORF1 74300360D38F371E PFAM PF05208 ALG3 NA ? IPR007873 unintegrated Cellular... Component: endoplasmic reticulum (GO:0005783)|Cellular Component: integral to membrane (GO:0016021) ...

  14. InterProScan Result: FS906632 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS906632 FS906632_3_ORF2 2C529C8D33AE78A2 PFAM PF07962 Swi3 1e-25 T IPR012923 Replication fork protection...to DNA damage stimulus (GO:0006974)|Biological Process: cell cycle (GO:0007049)|Biological Process: replication fork protection (GO:0048478) ...

  15. InterProScan Result: FS763011 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS763011 FS763011_3_ORF1 ADA83816196D1572 PANTHER PTHR21229 LUNG SEVEN TRANSMEMBRAN...E RECEPTOR 1.2e-07 T IPR009637 Transmembrane receptor, eukaryota Cellular Component: integral to membrane (GO:0016021) ...

  16. Fully integrated analysis of reactor kinetics, thermalhydraulics and the reactor control system in the MAPLE-X10 research reactor

    International Nuclear Information System (INIS)

    Shim, S.Y.; Carlson, P.A.; Baxter, D.K.

    1992-01-01

    A prototype research reactor, designated MAPLE-X10 (Multipurpose Applied Physics Lattice Experimental - X 10MW), is currently being built at AECL's Chalk River Laboratories. The CATHENA (Canadian Algorithm for Thermalhydraulic Network Analysis) two-fluid code was used in the safety analysis of the reactor to determine the adequacy of core cooling during postulated reactivity and loss-of-forced-flow transients. The system responses to a postulated transient are predicted including the feedback between reactor kinetics, thermalhydrauilcs and the reactor control systems. This paper describes the MAPLE-X10 reactor and the modelling methodology used. Sample simulations of postulated loss-of-heat-sink and loss-of-regulation transients are presented. (author)

  17. Design study on sodium-cooled middle-scale modular reactor

    International Nuclear Information System (INIS)

    Kisohara, Naoyuki; Hishida, Masahiko; Nibe, Nobuaki

    2003-09-01

    In Phase 1 of the 'Feasibility Study on Commercialized Fast Reactor Cycle Systems (F/S)', an advanced loop type reactor has been selected as a promising concept of sodium-cooled middle-scale modular reactor, which has a possibility to fulfill the design requirements of the F/S. This report summarizes the results of the design study on the sodium-cooled middle-scale modular reactor performed in JFY2002, which is the second year of Phase 2. The construction cost of the sodium-cooled middle-scale modular reactor, which has been constructed in JFY2002, was almost achieved the economical goal. But its achievability was not sufficient to accept the concept. In order to reduce the construction cost, the plant concept has been re-constructed based on the 50 MWe plant studied in JFY2002. After that, fundamental specifications of main systems and components for the new concept have been set, and critical subjects have been examined and evaluated. In addition, in order to achieve the further cost reduction, the plant with simplified secondary system, the plant with electric magnetic pump in secondary system, and the fuel handling system are examined and evaluated. As a result of this study, the plant concept of the sodium-cooled middle-scale modular reactor has been constructed, which has a prospect to satisfy the economic goal (construction cost: less than 200,000 yens/kWe, etc.) and has a prospect to solve the critical subjects. From now on, reflecting the results of elemental experiments, the preliminary conceptual design of this plant will be preceded toward the selection for narrowing down candidate concepts at the end of Phase 2. (author)

  18. EST Table: FS779999 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS779999 E_FL_fcaL_32K04_R_0 10/09/28 100 %/145 aa dbj|BAG30799.1| actin [Papilio x...locus:act- 2#actin#status:Confirmed#UniProt:P10984#protein_id:CAB04 675.1 10/09/10 100 %/145 aa AGAP005095-PA Protein|2L:9969318:99

  19. InterProScan Result: FS739298 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS739298 FS739298_4_ORF2 E65DEA0712139D30 PFAM PF00067 p450 3.3e-19 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  20. InterProScan Result: FS733119 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS733119 FS733119_3_ORF1 FBEF91F3CDA644D7 PRINTS PR00385 P450 1.7e-13 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  1. InterProScan Result: FS807624 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS807624 FS807624_3_ORF2 727CB335F709D390 PFAM PF00067 p450 3.4e-19 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  2. InterProScan Result: FS765894 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS765894 FS765894_3_ORF2 2218C53708677A45 PANTHER PTHR21229 LUNG SEVEN TRANSMEMBRAN...E RECEPTOR 7.9e-11 T IPR009637 Transmembrane receptor, eukaryota Cellular Component: integral to membrane (GO:0016021) ...

  3. InterProScan Result: FS932451 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS932451 FS932451_2_ORF2 773A43AAFA4CCB66 PANTHER PTHR10082:SF12 INTEGRIN BETA-3 NA...0)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  4. InterProScan Result: FS773973 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS773973 FS773973_5_ORF1 95C70FFD3346651F PANTHER PTHR10082:SF12 INTEGRIN BETA-3 9e...7160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  5. SeaWiFS Postlaunch Calibration and Validation Analyses

    Science.gov (United States)

    Hooker, Stanford B. (Editor); Firestone, Elaine (Editor); McClain, Charles R.; Barnes, Robert A.; Eplee, Robert E., Jr.; Franz, Bryan A.; Hsu, N. Christina; Patt, Frederick S.; Pietras, Christophe M.; Robinson, Wayne D.

    2000-01-01

    The effort to resolve data quality issues and improve on the initial data evaluation methodologies of the SeaWiFS Project was an extensive one. These evaluations have resulted, to date, in three major reprocessings of the entire data set where each reprocessing addressed the data quality issues that could be identified up to the time of the reprocessing. Three volumes of the SeaWiFS Postlaunch Technical Report Series (Volumes 9, 10, and 11) are needed to document the improvements implemented since launch. Volume 10 continues the sequential presentation of postlaunch data analysis and algorithm descriptions begun in Volume 9. Chapter 1 of Volume 10 describes an absorbing aerosol index, similar to that produced by the Total Ozone Mapping Spectrometer (TOMS) Project, which is used to flag pixels contaminated by absorbing aerosols, such as, dust and smoke. Chapter 2 discusses the algorithm being used to remove SeaWiFS out-of-band radiance from the water-leaving radiances. Chapter 3 provides an itemization of all significant changes in the processing algorithms for each of the first three reprocessings. Chapter 4 shows the time series of global clear water and deep-water (depths greater than 1,000m) bio-optical and atmospheric properties (normalized water-leaving radiances, chlorophyll, atmospheric optical depth, etc.) based on the eight-day composites as a check on the sensor calibration stability. Chapter 5 examines the variation in the derived products with scan angle using high resolution data around Hawaii to test for residual scan modulation effects and atmospheric correction biases. Chapter 6 provides a methodology for evaluating the atmospheric correction algorithm and atmospheric derived products using ground-based observations. Similarly, Chapter 7 presents match-up comparisons of coincident satellite and in situ data to determine the accuracy of the water-leaving radiances, chlorophyll a, and K(490) products.

  6. InterProScan Result: FS920349 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS920349 FS920349_1_ORF2 460BA22BB7066E3D PANTHER PTHR21347 CLEFT LIP AND PALATE ASSOCIATED TRANSME...MBRANE PROTEIN-RELATED 6e-44 T IPR008429 Cleft lip and palate transmembrane 1 ...

  7. InterProScan Result: FS917145 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS917145 FS917145_2_ORF2 DB1A671B79D1A25B PFAM PF05208 ALG3 NA ? IPR007873 unintegrated Cellular... Component: endoplasmic reticulum (GO:0005783)|Cellular Component: integral to membrane (GO:0016021) ...

  8. The T-cell receptor beta chain CDR3 region of BV8S1/BJ1S5 transcripts in type 1 diabetes.

    Science.gov (United States)

    Naserke, H E; Durinovic-Bellò, I; Seidel, D; Ziegler, A G

    1996-01-01

    We recently described the T-cell receptor (TCR) beta chain CDR3 motif S-SDRLG-NQPQH (BV8S1-BJ1S5) in an islet-specific T-cell clone (K2.12) from a type 1 diabetic patient (AS). A similar motif (RLGNQ) was also reported in a T-cell clone of non-obese diabetic (NOD) mice by others. In order to determine the frequency of our motif in selected and unselected T-cell populations, we cloned and sequenced the CDR3 region of BV8S1-BJ1S5 transcripts. These transcripts were derived from unstimulated peripheral blood T lymphocytes from two type 1 diabetic patients (AS and FS) and their non-diabetic sibling (WS), as well as from an islet-specific T-cell line of one of the patients. In addition, we compared the structure and composition of the CDR3 region in BV8S1-BJ1S5 transcripts from peripheral blood T cells between the patients and their non-diabetic sibling (>50 sequences each). We found that 30% of the islet-specific T-cell line cDNA clones expressed the entire sequence-motif, whereas it was absent in the clones of unstimulated peripheral blood T cells from both patients and their non-diabetic sibling. The average length of the CDR3 region was shorter in the patients (mean AS 9.9, FS 9.9, versus WS 10.7, p = 0.0037) and the number of inserted nucleotides in N nucleotide addition at the DJ-junction lower (mean AS 3.5, FS 3. 2, versus WS 5.2, P = diabetic sibling. Moreover, the pattern of amino acid usage in the CDR3 region was dissimilar at positions 5 and 6, where polar amino acids predominated in both diabetic siblings. In contrast, basic amino acids are preferentially used at position 5 in the clones of the non-diabetic sibling. These data provide information on the general structure of the TCR(BV8S1-BJ1S5) CDR3 region in type 1 diabetes and may indicate differences in the amino and nucleic acid composition of the TCR beta chain CDR3 region between two type 1 diabetic patients and their non-diabetic sibling.

  9. Safety features of the MAPLE-X10 reactor design

    International Nuclear Information System (INIS)

    Lee, A.G.; Bishop, W.E.; Heeds, W.

    1990-09-01

    The MAPLE-X10 reactor is a D 2 0-reflected, H 2 0-cooled and -moderated pool-type reactor under construction at the Chalk River Nuclear Laboratories. This 10-MW reactor will produce key medical and industrial radio-isotopes such as 99 Mo, 125 I, and 192 Ir. As the prototype for the MAPLE research reactor concept, the reactor incorporates diverse safety features both inherent in the design and in the added engineered systems. The safety requirements are analogous to those of the Canadian CANDU power reactor since standards for the licensing of new research reactors have not been developed yet by the licensing authority in Canada

  10. InterProScan Result: FS829494 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS829494 FS829494_5_ORF1 A59F385AE3D6656D PRINTS PR00385 P450 3.5e-13 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  11. InterProScan Result: FS907382 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS907382 FS907382_1_ORF2 1C0441A9D0DDEE80 SUPERFAMILY SSF47798 Barrier-to-autointegration... factor, BAF 1.3e-44 T IPR004122 Barrier- to-autointegration factor, BAF Molecular Function: DNA binding (GO:0003677) ...

  12. InterProScan Result: FS856416 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS856416 FS856416_5_ORF1 8BC932287F58E2D2 PANTHER PTHR21229 LUNG SEVEN TRANSMEMBRAN...E RECEPTOR 3.7e-48 T IPR009637 Transmembrane receptor, eukaryota Cellular Component: integral to membrane (GO:0016021) ...

  13. InterProScan Result: FS860732 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS860732 FS860732_6_ORF1 0375CFA2D74CE0C2 PANTHER PTHR10082 INTEGRIN BETA SUBUNIT 3...-matrix adhesion (GO:0007160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  14. InterProScan Result: FS735919 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS735919 FS735919_4_ORF2 1C0441A9D0DDEE80 SUPERFAMILY SSF47798 Barrier-to-autointegration... factor, BAF 1.3e-44 T IPR004122 Barrier- to-autointegration factor, BAF Molecular Function: DNA binding (GO:0003677) ...

  15. CephFS: a new generation storage platform for Australian high energy physics

    Science.gov (United States)

    Borges, G.; Crosby, S.; Boland, L.

    2017-10-01

    This paper presents an implementation of a Ceph file system (CephFS) use case at the ARC Center of Excellence for Particle Physics at the Terascale (CoEPP). CoEPP’s CephFS provides a posix-like file system on top of a Ceph RADOS object store, deployed on commodity hardware and without single points of failure. By delivering a unique file system namespace at different CoEPP centres spread across Australia, local HEP researchers can store, process and share data independently of their geographical locations. CephFS is also used as the back-end file system for a WLCG ATLAS user area at the Australian Tier-2. Dedicated SRM and XROOTD services, deployed on top of CoEPP’s CephFS, integrates it in ATLAS data distributed operations. This setup, while allowing Australian HEP researchers to trigger data movement via ATLAS grid tools, also enables local posix-like read access providing greater control to scientists of their data flows. In this article we will present details on CoEPP’s Ceph/CephFS implementation and report performance I/O metrics collected during the testing/tuning phase of the system.

  16. EST Table: FS748350 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available PREDICTED: similar to fetal alzheimer antigen, falz [Nasonia vitripennis] 10/09/08 37 %/193 aa FBpp0290563|E...811424.1| PREDICTED: similar to fetal alzheimer antigen, falz [Tribolium castaneum] FS748350 caL- ...

  17. EST Table: FS911308 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS911308 E_FL_fufe_22N11_F_0 11/12/09 n.h 10/09/28 53 %/286 aa ref|XP_002092266.1| GE14...094 [Drosophila yakuba] gb|EDW91978.1| GE14094 [Drosophila yakuba] 10/09/12 53 %/286 aa FBpp0259104|DyakGE14

  18. EST Table: FS796494 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available 38 aa ref|XP_001945612.1| PREDICTED: similar to glucocerebrosidase, partial [Acyr...9/10 42 %/261 aa gi|91087345|ref|XP_975608.1| PREDICTED: similar to putative lysosomal glucocerebrosidase [Tribolium castaneum] FS796494 ffbm ...

  19. InterProScan Result: FS860732 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS860732 FS860732_6_ORF1 0375CFA2D74CE0C2 PRINTS PR01186 INTEGRINB 3.7e-20 T IPR015812 Integri...0)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  20. Dispersion management for a sub-10-fs, 10 TW optical parametric chirped-pulse amplifier.

    Science.gov (United States)

    Tavella, Franz; Nomura, Yutaka; Veisz, Laszlo; Pervak, Vladimir; Marcinkevicius, Andrius; Krausz, Ferenc

    2007-08-01

    We report the amplification of three-cycle, 8.5 fs optical pulses in a near-infrared noncollinear optical parametric chirped-pulse amplifier (OPCPA) up to energies of 80 mJ. Improved dispersion management in the amplifier by means of a combination of reflection grisms and a chirped-mirror stretcher allowed us to recompress the amplified pulses to within 6% of their Fourier limit. The novel ultrabroad, ultraprecise dispersion control technology presented in this work opens the way to scaling multiterawatt technology to even shorter pulses by optimizing the OPCPA bandwidth.

  1. EST Table: FS914945 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS914945 E_FL_fufe_33M09_F_0 10/09/28 36 %/210 aa ref|XP_001842174.1| sensitized chromosome inheritance... modifier 19 [Culex quinquefasciatus] gb|EDS39679.1| sensitized chromosome inheritance m

  2. EST Table: FS918359 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS918359 E_FL_fufe_44C07_F_0 10/09/28 37 %/227 aa ref|XP_001842174.1| sensitized chromosome inheritance... modifier 19 [Culex quinquefasciatus] gb|EDS39679.1| sensitized chromosome inheritance m

  3. EST Table: FS891235 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS891235 E_FL_ftes_02B20_R_0 11/12/09 GO hit GO:0003779(actin binding)|GO:0007010(cytoskeleton... organization)|GO:0015629(actin cytoskeleton)|GO:0030036(actin cytoskeleton organization) 10/09/2

  4. EST Table: FS904516 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available 1461 10/09/10 48 %/243 aa gnl|Amel|GB18846-PA 10/09/10 46 %/242 aa gi|91086187|ref|XP_971225.1| PREDICTED: similar to medulloblastoma...oblastoma antigen MU-MB-50.4 [Tribolium castaneum] gb|EFA06682.1| hypothetical prot...FS904516 E_FL_fufe_02D20_F_0 11/12/09 n.h 10/09/28 46 %/242 aa ref|XP_971225.1| PREDICTED: similar to medull

  5. Waste generated by the future decommissioning of the Magurele VVR-S Research Reactor

    International Nuclear Information System (INIS)

    Dragolici, F.; Turcanu, C.N.; Dragolici, A.C.

    2001-01-01

    Nuclear Research Reactor WWR-S from the National Institute of Research and Development for Physics and Nuclear Engineering 'Horia Hulubei', Bucharest-Magurele, was commissioned in July 1957 and it was shut down in December 1997. At the moment the reactor is in conservation state. During its operation this reactor worked at an average power of 2MW, almost 3216 h/year, producing a total thermal power of 230 x 10 3 MWh. No major modifications or improvements were made during the 40 years of operation to the essential parts of the reactor, respective to the primary cooling system, reactor vessel, active core and electronic devices. So, all components of the measure, control and protection systems are old, generally at the technical level of the 1950s, therefore a reason why in December 1997 the operation was ceased. At present, the reactor can be considered, by IAEA definition in the first stage (reactor shut down, but the vital functions are maintained and monitored). The survey is related to the second stage - restrictive use of the area. To develop a real decommissioning project, it was first necessary to evaluate the volume and the characteristics of the radioactive waste which will be generated. Radioactive waste generated during the decommissioning of Magurele WR-S research reactor may be classified as: Activated wastes (internal structures, horizontal channels and thermal column, biological shield); Contaminated wastes (primary circuit non-activated components, hot cells, some technological rooms as main hall, pumps room, radioactive material transfer areas, ventilation building and stack); Possibly contaminated materials from any area of reactor building and ventilation building. After 40 years of nuclear research activities, all such areas are suspected of contamination. The volume of wastes that will result from WWR-S Research Reactor decommissioning is summarized

  6. Safety features of the MAPLE-X10 reactor design

    International Nuclear Information System (INIS)

    Lee, A.G.; Bishop, W.E.; Heeds, W.

    1990-01-01

    This paper reports on the MAPLE-X10 reactor D 2 O-reflected, H 2 O-cooled and -moderated pool- type reactor, under construction at the Chalk River Nuclear Laboratories. This 10-MW will produce key medical and industrial radioisotopes such as 99 Mo, 125 I, and 192 Ir. The prototype for the MAPLE research reactor concept, the reactor incorporates diverse safety features both inherent in the design and in the added engineered systems. The safety requirements are analogous to those of the Canadian CANDU power reactor as standards for the licensing of new research reactors have not been developed by the licensing authority in Canada

  7. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 15, 2011, 10:00 PM status

    International Nuclear Information System (INIS)

    2011-01-01

    This situation note is established according to the information gained on March 15, 2011, at 10:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 and of the spent fuel pools of reactors No. 4, 5 and 6 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  8. EST Table: FS884513 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS884513 E_FL_ftes_30F14_F_0 10/09/28 31 %/166 aa ref|XP_002572677.1| nuclear movement... protein related [Schistosoma mansoni] emb|CAZ28909.1| nuclear movement protein related [Schistosoma mans

  9. EST Table: FS758854 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS758854 E_FL_fcaL_09I20_F_0 10/09/28 35 %/195 aa ref|XP_001842174.1| sensitized chromosome inheritance... modifier 19 [Culex quinquefasciatus] gb|EDS39679.1| sensitized chromosome inheritance m

  10. EST Table: FS805970 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available milar to xaa-pro dipeptidase app(e.coli) [Nasonia vitripennis] 10/09/09 47 %/178 aa FBpp0123641|DanaGF20449-...PREDICTED: similar to xaa-pro dipeptidase app(e.coli) [Tribolium castaneum] FS727105 fmgV ...

  11. Calibration of SeaWiFS after two years on orbit

    Science.gov (United States)

    Barnes, Robert A.; McClain, Charles R.

    1999-12-01

    The Sea-viewing Wide Field-of-view Sensor (SeaWiFS) was launched on 1 August 1997, and the first Earth images were taken on 4 September 1997. Regular, daily measurements of the sun, via the onboard diffuser, started on 9 September 1997 and regular, monthly measurements of the moon on November 14, 1997. These lunar measurements, as first reported at EUROPTO'98, provide a highly sensitive method for determining the change in the radiometric sensitivity of SeaWiFS. The prelaunch radiometric calibration used by SeaWiFS was performed in the Spring of 1997 at the spacecraft manufacturer's facility. The calibration measurements were made by a team from the National Institute of Standards and Technology (NIST) and the SeaWiFS Project. The uncertainties in this calibration range from 2% to 3% for the eight SeaWiFS bands. In addition, a set of outdoor measurements of the sun were made at the instrument manufacturer's facility in November 1993, just before the delivery of SeaWiFS to the spacecraft manufacturer. These solar measurements, using the instrument's diffuser, were combined with a separate set of solar radiometer measurements to determine the transmittance of the atmosphere. At the start of on-orbit measurements by SeaWiFS, solar measurements were made again by the instrument. These two sets of measurements make up the transfer-to-orbit experiment. From the ground measurements, the outputs of the SeaWiFS bands on orbit were predicted. For each band, the output from the initial on-orbit measurements agree with the predicted values by 21/2% or less. The uncertainties for the transfer-to-orbit experiment are estimated to be approximately 3% to 4%. From 14 November 1997 to 29 June 1999, SeaWiFS has made 20 measurements of the moon. The analysis of lunar measurements presented here has minor modifications to that presented at EUROPTO'98. The trend lines from the current analysis have been extrapolated back from 14 November 1997 to 4 September 1997 to describe the changes

  12. The crystal structure of Kirkiite, Pb10Bi3As3S19

    DEFF Research Database (Denmark)

    Makovicky, Emil; Balic Zunic, Tonci; Karanovic, Ljiljana

    2006-01-01

    and chemical analysis resulted in comparable formulae, Pb10Bi2.16As3.84S19 and Pb10.08Bi2.55Sb0.13As2.91S19, respectively, which are close to the ideal formula Pb10Bi3As3S19. The crystal lattice shows a pseudohexagonal symmetry, which is the cause of common twinning in this mineral. The main twin-law has (20...... layers parallel to (083) of kirkiite; the slabs are unit-cell-twinned on (010) refl ection planes. The structure contains one split As position, and two additional sites that could accommodate both As and Bi. The As,Bi distribution over these two sites is determined by the trapezoidal distortion...... of the half-octahedral coordination environment inside the tightly bonded double layers of the PbS-SnS archetype slabs. Owing to the stoichiometry requirements in this structure, Bi must also substitute for 1/11 of the Pb sites. Bond-valence calculations and the volumes of coordination polyhedra show...

  13. EST Table: FS916089 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS916089 E_FL_fufe_37E08_F_0 10/09/28 43 %/186 aa ref|XP_001843810.1| mediator comp...lex [Culex quinquefasciatus] gb|EDS34592.1| mediator complex [Culex quinquefasciatus] 10/09/12 36 %/187 aa F...1082463|ref|XP_971521.1| PREDICTED: similar to mediator complex [Tribolium castaneum] BJ984999 fufe ...

  14. InterProScan Result: FS769068 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS769068 FS769068_2_ORF2 CC628FD86337D2E6 PFAM PF03998 Utp11 5.3e-70 T IPR007144 Small-subunit process...ome, Utp11 Biological Process: rRNA processing (GO:0006364)|Cellular Component: small-subunit processome (GO:0032040) ...

  15. EST Table: FS772438 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available 0040007(growth) 10/09/28 30 %/138 aa ref|XP_966819.1| PREDICTED: similar to myostatin [Tribolium castaneum] ... 30 %/138 aa gi|91085397|ref|XP_966819.1| PREDICTED: similar to myostatin [Tribolium castaneum] FS772438 fcaL ...

  16. U.S. and foreign breeder reactors

    International Nuclear Information System (INIS)

    Hill, E.H.

    1977-01-01

    The running battle between Congress and the Administration over the Clinch River Breeder Reactor Plant (CRBRP) Project has provoked an increased interest in domestic and foreign breeder reactor programs. Perhaps an understanding of the history of breeders here and abroad will serve to place the CRBRP in perspective and allow some analysis of how the U.S. appears on the global canvas. Breeder reactor technology has, for the most part, settled down to concentration on the liquid metal fast breeder reactor (LMFBR). This is the result of 32 years of experience with reactors employing a fast neutron flux and even longer experience with liquid metal coolants. However, a number of U.S. utilities are sponsoring a gas cooled fast reactor program as an alternative technology to the LMFBR. This development program is supported by the U.S. Department of Energy

  17. Test reactor: basic to U.S. breeder reactor development

    International Nuclear Information System (INIS)

    Miller, B.J.; Harness, A.J.

    1975-01-01

    Long-range energy planning in the U. S. includes development of a national commercial breeder reactor program. U. S. development of the LMFBR is following a conservative sequence of extensive technology development through use of test reactors and demonstration plants prior to construction of commercial plants. Because materials and fuel technology development is considered the first vital step in this sequence, initial U. S. efforts have been directed to the design and construction of a unique test reactor. The Fast Flux Test Facility, FFTF, is a 400 MW(t) reactor with driver fuel locations, open test locations, and closed loops for higher risk experiments. The FFTF will provide a prototypic LMFBR core environment with sufficient instrumentation for detailed core environmental characterization and a testing capability substituted for breeder capability. The unique comprehensive fuel and materials testing capability of the FFTF will be key to achieving long-range objectives of increased power density, improved breeding gain and shorter doubling times. (auth)

  18. EST Table: FS911502 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available eritance modifier 19 [Culex quinquefasciatus] gb|EDS39679.1| sensitized chromosome inheritance...FS911502 E_FL_fufe_23G14_F_0 11/12/09 n.h 10/09/28 35 %/234 aa ref|XP_001842174.1| sensitized chromosome inh

  19. EST Table: FS905368 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available ar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] gb|EEZ97704.1| budding uninhibited by benzimidazoles...|XP_970295.1| PREDICTED: similar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] FS920882 fufe ...

  20. EST Table: FS931361 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available ar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] gb|EEZ97704.1| budding uninhibited by benzimidazoles...|XP_970295.1| PREDICTED: similar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] FS920882 fwgP ...

  1. EST Table: FS765476 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available ar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] gb|EEZ97704.1| budding uninhibited by benzimidazoles...|XP_970295.1| PREDICTED: similar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] FS920882 fcaL ...

  2. EST Table: FS791348 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available ar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] gb|EEZ97704.1| budding uninhibited by benzimidazoles...|XP_970295.1| PREDICTED: similar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] FS920882 ffbm ...

  3. EST Table: FS909643 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available ar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] gb|EEZ97704.1| budding uninhibited by benzimidazoles...|XP_970295.1| PREDICTED: similar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] FS920882 fufe ...

  4. InterProScan Result: FS932674 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS932674 FS932674_3_ORF2 C43825172FE72B67 PFAM PF00067 p450 0.00014 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  5. Comparative Genome Analyses of Serratia marcescens FS14 Reveals Its High Antagonistic Potential

    Science.gov (United States)

    Li, Pengpeng; Kwok, Amy H. Y.; Jiang, Jingwei; Ran, Tingting; Xu, Dongqing; Wang, Weiwu; Leung, Frederick C.

    2015-01-01

    S. marcescens FS14 was isolated from an Atractylodes macrocephala Koidz plant that was infected by Fusarium oxysporum and showed symptoms of root rot. With the completion of the genome sequence of FS14, the first comprehensive comparative-genomic analysis of the Serratia genus was performed. Pan-genome and COG analyses showed that the majority of the conserved core genes are involved in basic cellular functions, while genomic factors such as prophages contribute considerably to genome diversity. Additionally, a Type I restriction-modification system, a Type III secretion system and tellurium resistance genes are found in only some Serratia species. Comparative analysis further identified that S. marcescens FS14 possesses multiple mechanisms for antagonism against other microorganisms, including the production of prodigiosin, bacteriocins, and multi-antibiotic resistant determinants as well as chitinases. The presence of two evolutionarily distinct Type VI secretion systems (T6SSs) in FS14 may provide further competitive advantages for FS14 against other microbes. To our knowledge, this is the first report of comparative analysis on T6SSs in the genus, which identifies four types of T6SSs in Serratia spp.. Competition bioassays of FS14 against the vital plant pathogenic bacterium Ralstonia solanacearum and fungi Fusarium oxysporum and Sclerotinia sclerotiorum were performed to support our genomic analyses, in which FS14 demonstrated high antagonistic activities against both bacterial and fungal phytopathogens. PMID:25856195

  6. Comparative genome analyses of Serratia marcescens FS14 reveals its high antagonistic potential.

    Science.gov (United States)

    Li, Pengpeng; Kwok, Amy H Y; Jiang, Jingwei; Ran, Tingting; Xu, Dongqing; Wang, Weiwu; Leung, Frederick C

    2015-01-01

    S. marcescens FS14 was isolated from an Atractylodes macrocephala Koidz plant that was infected by Fusarium oxysporum and showed symptoms of root rot. With the completion of the genome sequence of FS14, the first comprehensive comparative-genomic analysis of the Serratia genus was performed. Pan-genome and COG analyses showed that the majority of the conserved core genes are involved in basic cellular functions, while genomic factors such as prophages contribute considerably to genome diversity. Additionally, a Type I restriction-modification system, a Type III secretion system and tellurium resistance genes are found in only some Serratia species. Comparative analysis further identified that S. marcescens FS14 possesses multiple mechanisms for antagonism against other microorganisms, including the production of prodigiosin, bacteriocins, and multi-antibiotic resistant determinants as well as chitinases. The presence of two evolutionarily distinct Type VI secretion systems (T6SSs) in FS14 may provide further competitive advantages for FS14 against other microbes. To our knowledge, this is the first report of comparative analysis on T6SSs in the genus, which identifies four types of T6SSs in Serratia spp.. Competition bioassays of FS14 against the vital plant pathogenic bacterium Ralstonia solanacearum and fungi Fusarium oxysporum and Sclerotinia sclerotiorum were performed to support our genomic analyses, in which FS14 demonstrated high antagonistic activities against both bacterial and fungal phytopathogens.

  7. CORRELATIONS BETWEEN HOMOLOGUE CONCENTRATIONS OF PCDD/FS AND TOXIC EQUIVALENCY VALUES IN LABORATORY-, PACKAGE BOILER-, AND FIELD-SCALE INCINERATORS

    Science.gov (United States)

    The toxic equivalency (TEQ) values of polychlorinated dibenzo-p-dioxins and polychlorinated dibenzofurans (PCDD/Fs) are predicted with a model based on the homologue concentrations measured from a laboratory-scale reactor (124 data points), a package boiler (61 data points), and ...

  8. EST Table: FS789999 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS789999 E_FL_ffbm_02F05_F_0 10/09/28 42 %/246 aa ref|XP_971541.1| PREDICTED: simil...ar to AGAP008392-PA [Tribolium castaneum] gb|EFA09946.1| hypothetical protein TcasGA2_TC012099 [Tribolium ca

  9. InterProScan Result: FS828147 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS828147 FS828147_5_ORF1 7B963168B4634A1D PRINTS PR00385 P450 2.3e-13 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  10. InterProScan Result: FS828147 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS828147 FS828147_5_ORF1 7B963168B4634A1D PFAM PF00067 p450 1.3e-61 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  11. InterProScan Result: FS777434 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS777434 FS777434_4_ORF1 546CBAAA77BF4D8A PRINTS PR00385 P450 3.7e-11 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  12. InterProScan Result: FS760705 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS760705 FS760705_3_ORF2 BCE542E7B7154334 PFAM PF00067 p450 6.5e-36 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  13. InterProScan Result: FS874329 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS874329 FS874329_4_ORF1 93DDB3924654C140 PFAM PF00067 p450 3.6e-36 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  14. Pebble bed reactors simulation using MCNP: The Chinese HTR-10 reactor

    Directory of Open Access Journals (Sweden)

    SA Hosseini

    2013-09-01

    Full Text Available   Given the role of Gas-Graphite reactors as the fourth generation reactors and their recently renewed importance, in 2002 the IAEA proposed a set of Benchmarking problems. In this work, we propose a model both efficient in time and resources and exact to simulate the HTR-10 reactor using MCNP-4C code. During the present work, all of the pressing factors in PBM reactor design such as the inter-pebble leakage, fuel particle distribution and fuel pebble packing fraction effects have been taken into account to obtain an exact and easy to run model. Finally, the comparison between the results of the present work and other calculations made at INEEL proves the exactness of the proposed model.

  15. Emission of PCDD/Fs and dioxin-like PCBs from metallurgy industries in S. Korea.

    Science.gov (United States)

    Yu, Byeong-Woon; Jin, Guang-Zhu; Moon, Young-Hoon; Kim, Min-Kwan; Kyoung, Jong-Dai; Chang, Yoon-Seok

    2006-01-01

    The metallurgy industry and municipal waste incinerators are considered the main sources of polychlorinated dibenzo-p-dioxin and dibenzofurans (PCDD/Fs) in many countries. This study investigated the emission factors and total emissions of PCDD/Fs and dioxin-like polychlorinated biphenyls (PCBs) emitted from metallurgy industries (including ferrous and nonferrous foundries) in Korea. The toxic equivalency (TEQ) emission factor of PCDD/Fs was the highest for secondary copper production, at 24451 ng I-TEQ/ton. The total estimated emissions of PCDD/Fs from these sources were 35.259 g I-TEQ/yr, comprising 0.088 g I-TEQ/yr from ferrous foundries, 31.713 g I-TEQ/yr from copper production, 1.716 g I-TEQ/yr from lead production, 0.111 g I-TEQ/yr from zinc production, and 1.631 g I-TEQ/yr from aluminum production. The total estimated annual amounts of dioxin-like PCBs emitted from these sources were 13.260 g WHO-TEQ/yr, comprising 0.014 g WHO-TEQ/yr from ferrous foundries, 12.675 g WHO-TEQ/yr from copper production, 0.170 g WHO-TEQ/yr from lead production, 0.017 g WHO-TEQ/yr from zinc production, and 0.384 g WHO-TEQ/yr from aluminum production. The highest emission factor was found for secondary copper smelting, at 9770 ng WHO-TEQ/ton.

  16. The nuclear design of the MAPLE-X10 reactor

    International Nuclear Information System (INIS)

    Heeds, W.; Lebenhaft, J.R.; Lee, A.G.; Carlson, P.A.; McIlvain, H.; Lidstone, R.F.

    1995-01-01

    AECL is currently building the 10-MW MAPLE-X10 reactor at the Chalk River Laboratories to operate as a dedicated producer of commercial-scale quantities of key medical and industrial radioisotopes and as a demonstration of the MAPLE reactor design. In support of the safety and licensing analyses, static physics calculations have been performed to determine the neutronic performance and safety characteristics of the MAPLE-X10 reactor. This report summarizes results from the static physics calculations for several core conditions prior to commencing radioisotope production. (author)

  17. EST Table: FS871051 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available aa ref|NP_001139536.1| mortality factor 4-like [Bombyx mori] gb|ABJ99463.1| mrg15-like protein [Bombyx mori...FS871051 E_FL_fner_44F14_R_0 11/12/09 GO hit GO:0005634(nucleus) 10/09/28 100 %/257

  18. EST Table: FS880151 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available to DNA mismatch repair protein pms2 [Acyrthosiphon pisum] 10/09/11 63 %/127 aa FBpp0252351|DwilGK23208-PA 1...aa gi|91079030|ref|XP_974934.1| PREDICTED: similar to DNA mismatch repair protein pms2 [Tribolium castaneum] FS880151 ftes ...

  19. EST Table: FS895236 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available match repair)|GO:0030983(mismatched DNA binding) 10/09/28 68 %/141 aa ref|XP_001663861.1| DNA mismatch repair protein pms2... [Aedes aegypti] gb|EAT34048.1| DNA mismatch repair protein pms2 [Aedes aegypti] 10/09/12 62 %...1 %/140 aa gi|91079030|ref|XP_974934.1| PREDICTED: similar to DNA mismatch repair protein pms2 [Tribolium castaneum] FS895236 ftes ...

  20. InterProScan Result: FS817458 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS817458 FS817458_1_ORF1 B27ECCF086D27F4E PFAM PF00067 p450 3.1e-28 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  1. Efficiency and safety of OctreotidLong FS therapy in acromegaly patients

    Directory of Open Access Journals (Sweden)

    A V Dreval’

    2013-03-01

    Full Text Available Aim of this study was to investigate efficiency and safety of OctreotidLong FS in patients with acromegaly. Materials and methods. 41 patients with acromegaly (8 – de novo and 33 patients after different somato statin analogs treatment was treated OctreotidLong FS one injection in 28 days. Growth hormone (GH, Insulin like Growth Factor 1 (IFG1, fasting glucose (FG and HbA1c were assess after 3, 6 and 12 month of therapy. Results. We found out the decreasing of GH and IGF1 from 12,8 (8,0–82,7 mU/ml to 3,8 (1,6–13,8 mU/ml ( p < 0,05 and %IGF1 increasing (% IGF1 from 231 (150–286% to 9,5 (−26–111% ( p < 0,05 in 8 de novo acromegalic patients. We also revealed that IGF1 didn’t change and GH decreased after 3 month (33 patients, 6 month (22 patients and 12 month (8 patients of OctreotidLong FS treatment. We didn’t observed negative effect of OctreotidLong FS treatment to carbohydrate metabolism in patients with acromegaly. Conclusion. The therapy of OctreotidLong FS leads to induce successful control of GH and IGFI in 50% de novo patients and didn’t change the number of patients with control of acromegaly after another somato statin analogs treatment. Carbohydrate metabolism also didn’t change after OctreotidLong FS treatment.

  2. SeaWiFS_L3m_R32_PIC_9km

    Data.gov (United States)

    National Aeronautics and Space Administration — The SeaWiFS instrument was launched by Orbital Sciences Corporation on the OrbView-2 (a.k.a. SeaStar) satellite in August 1997, and collected data from September...

  3. New class of compact diode pumped sub 10 fs lasers for biomedical applications

    DEFF Research Database (Denmark)

    Le, T.; Mueller, A.; Sumpf, B.

    2016-01-01

    Diode-pumping Ti: sapphire lasers promises a new approach to low-cost femtosecond light sources. Thus in recent years much effort has been taken just to overcome the quite low power and low beam qualities of available green diodes to obtain output powers of several hundred milliwatts from a fs-la...

  4. FS65 Disposition Option Report

    Energy Technology Data Exchange (ETDEWEB)

    Wenz, Tracy R. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-09-25

    This report outlines the options for dispositioning the MOX fuel stored in FS65 containers at LANL. Additional discussion regarding the support equipment for loading and unloading the FS65 transport containers is included at the end of the report.

  5. U.S. Domestic Reactor Conversion Programs

    International Nuclear Information System (INIS)

    Woolstenhulme, Eric

    2008-01-01

    The Conversion Projects Include: the revision of the facilities safety basis documents and supporting analysis, the fabrication of new LEU fuel, the change-out of the reactor core, and the removal of the used HEU fuel (by INL University Fuels Program or DOE-NE). The major entities involved are: the U.S. Nuclear Regulatory Commission, the University reactor department, the fuel and hardware fabricators, the Spent fuel receipt facilities, the Spent fuel shipping services, and the U.S. Department of Energy and their subcontractors. Three major Reactor Conversion Program milestones have been accomplished since 2006: the conversion of the TRIGA reactor at Texas A and M University Nuclear Science Center, the conversion of the University of Florida Training Reactor, and the conversion of the Purdue University Reactor. Four Reactor Conversion Program milestones yet to be accomplished in 2008 and 2009: the Washington State University Nuclear Radiation Center reactor, the Oregon State University TRIGA Reactor, the University of Wisconsin Nuclear Reactor, and the Neutron Radiography Reactor Facility. NNSA is committed to doing things cheaper, better, smarter, safer through a 'Lessons Learned' process. The conversion team assessed each major activity grouping: Project Initiation, Conversion Proposal Development, Fuel Fabrication and Hardware, Core Conversion, and Spent Nuclear Fuel Removal. Issues were identified and recommendations were given

  6. Comparative genome analyses of Serratia marcescens FS14 reveals its high antagonistic potential.

    Directory of Open Access Journals (Sweden)

    Pengpeng Li

    Full Text Available S. marcescens FS14 was isolated from an Atractylodes macrocephala Koidz plant that was infected by Fusarium oxysporum and showed symptoms of root rot. With the completion of the genome sequence of FS14, the first comprehensive comparative-genomic analysis of the Serratia genus was performed. Pan-genome and COG analyses showed that the majority of the conserved core genes are involved in basic cellular functions, while genomic factors such as prophages contribute considerably to genome diversity. Additionally, a Type I restriction-modification system, a Type III secretion system and tellurium resistance genes are found in only some Serratia species. Comparative analysis further identified that S. marcescens FS14 possesses multiple mechanisms for antagonism against other microorganisms, including the production of prodigiosin, bacteriocins, and multi-antibiotic resistant determinants as well as chitinases. The presence of two evolutionarily distinct Type VI secretion systems (T6SSs in FS14 may provide further competitive advantages for FS14 against other microbes. To our knowledge, this is the first report of comparative analysis on T6SSs in the genus, which identifies four types of T6SSs in Serratia spp.. Competition bioassays of FS14 against the vital plant pathogenic bacterium Ralstonia solanacearum and fungi Fusarium oxysporum and Sclerotinia sclerotiorum were performed to support our genomic analyses, in which FS14 demonstrated high antagonistic activities against both bacterial and fungal phytopathogens.

  7. EST Table: FS799999 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS799999 E_FL_fmgV_02M15_F_0 10/09/28 100 %/197 aa ref|NP_001036966.1| lipase-1 [Bo...mbyx mori] dbj|BAC00960.1| lipase-1 [Bombyx mori] gb|AAZ66799.1| lipase [Samia cynthia ricini] gb|ABB90967.1

  8. EST Table: FS773562 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available /09/28 91 %/214 aa ref|NP_001036831.1| saposin-related [Bombyx mori] dbj|BAA23126.1| BmP109 [Bombyx mori] 10...0 38 %/197 aa gi|91077504|ref|XP_966852.1| PREDICTED: similar to saposin isoform 1 [Tribolium castaneum] FS773562 fcaL ...

  9. RAZORBACK - A Research Reactor Transient Analysis Code Version 1.0 - Volume 3: Verification and Validation Report.

    Energy Technology Data Exchange (ETDEWEB)

    Talley, Darren G.

    2017-04-01

    This report describes the work and results of the verification and validation (V&V) of the version 1.0 release of the Razorback code. Razorback is a computer code designed to simulate the operation of a research reactor (such as the Annular Core Research Reactor (ACRR)) by a coupled numerical solution of the point reactor kinetics equations, the energy conservation equation for fuel element heat transfer, the equation of motion for fuel element thermal expansion, and the mass, momentum, and energy conservation equations for the water cooling of the fuel elements. This V&V effort was intended to confirm that the code shows good agreement between simulation and actual ACRR operations.

  10. Preliminary studies on fast particle diagnostics for the future fs-laser facility at PALS

    Czech Academy of Sciences Publication Activity Database

    Margarone, Daniele; Krása, Josef; Láska, Leoš; Velyhan, Andriy; Mocek, Tomáš; Torrisi, L.; Ando, L.; Gammino, S.; Prokůpek, J.; Krouský, Eduard; Pfeifer, Miroslav; Ullschmied, Jiří; Rus, Bedřich

    2010-01-01

    Roč. 165, 6-10 (2010), s. 419-428 ISSN 1042-0150 R&D Projects: GA AV ČR IAA100100715 Institutional research plan: CEZ:AV0Z10100523; CEZ:AV0Z20430508 Keywords : fs-laser plasma * electron streams * ion streams * electron spectrometer * ion collectors Subject RIV: BL - Plasma and Gas Discharge Physics Impact factor: 0.660, year: 2010

  11. Neutron dose rate analysis on HTGR-10 reactor using Monte Carlo code

    Science.gov (United States)

    Suwoto; Adrial, H.; Hamzah, A.; Zuhair; Bakhri, S.; Sunaryo, G. R.

    2018-02-01

    The HTGR-10 reactor is cylinder-shaped core fuelled with kernel TRISO coated fuel particles in the spherical pebble with helium cooling system. The outlet helium gas coolant temperature outputted from the reactor core is designed to 700 °C. One advantage HTGR type reactor is capable of co-generation, as an addition to generating electricity, the reactor was designed to produce heat at high temperature can be used for other processes. The spherical fuel pebble contains 8335 TRISO UO2 kernel coated particles with enrichment of 10% and 17% are dispersed in a graphite matrix. The main purpose of this study was to analysis the distribution of neutron dose rates generated from HTGR-10 reactors. The calculation and analysis result of neutron dose rate in the HTGR-10 reactor core was performed using Monte Carlo MCNP5v1.6 code. The problems of double heterogeneity in kernel fuel coated particles TRISO and spherical fuel pebble in the HTGR-10 core are modelled well with MCNP5v1.6 code. The neutron flux to dose conversion factors taken from the International Commission on Radiological Protection (ICRP-74) was used to determine the dose rate that passes through the active core, reflectors, core barrel, reactor pressure vessel (RPV) and a biological shield. The calculated results of neutron dose rate with MCNP5v1.6 code using a conversion factor of ICRP-74 (2009) for radiation workers in the radial direction on the outside of the RPV (radial position = 220 cm from the center of the patio HTGR-10) provides the respective value of 9.22E-4 μSv/h and 9.58E-4 μSv/h for enrichment 10% and 17%, respectively. The calculated values of neutron dose rates are compliant with BAPETEN Chairman’s Regulation Number 4 Year 2013 on Radiation Protection and Safety in Nuclear Energy Utilization which sets the limit value for the average effective dose for radiation workers 20 mSv/year or 10μSv/h. Thus the protection and safety for radiation workers to be safe from the radiation source has

  12. Displacement sensor for measurement of fuel rod elongation in the LOFT reactors

    International Nuclear Information System (INIS)

    Billeter, T.R.

    1979-09-01

    Qualification tests conducted for a period of 700 hours of each of three displacement measuring (LVDT) sensors confirmed applicability of the design for use in the Loss-of-Fluid-Test (LOFT) reactor. Operationally, the sensor satisfies all specified requirements for LOFT. Even for imposed temperature transients at rates up to 100 0 F/s, the indicated displacement remained within the allowed maximum error band of +- 10% of reading. The 0.6-inch O.D. by 5.5-inch long sensor exhibited a linearly related signal output variation for displacement variations of up to 1-inch range. Long term operation at temperatures of 100 0 F to 800 0 F caused no perceptible permanent change of operating characteristics

  13. Measurement of the $B^0_s-\\overline{B}^0_s$ oscillation frequency $\\Delta m_s$ in $B^0_s \\to D^-_s (3)\\pi$ decays

    CERN Document Server

    INSPIRE-00258707; Adeva, B.; Adinolfi, M.; Adrover, C.; Affolder, A.; Ajaltouni, Z.; Albrecht, J.; Alessio, F.; Alexander, M.; Alkhazov, G.; Alvarez Cartelle, P.; Alves Jr, A.A.; Amato, S.; Amhis, Y.; Anderson, J.; Appleby, R.B.; Aquines Gutierrez, O.; Archilli, F.; Arrabito, L.; Artamonov, A.; Artuso, M.; Aslanides, E.; Auriemma, G.; Bachmann, S.; Back, J.J.; Bailey, D.S.; Balagura, V.; Baldini, W.; Barlow, R.J.; Barschel, C.; Barsuk, S.; Barter, W.; Bates, A.; Bauer, C.; Bauer, Th.; Bay, A.; Bediaga, I.; Belous, K.; Belyaev, I.; Ben-Haim, E.; Benayoun, M.; Bencivenni, G.; Benson, S.; Benton, J.; Bernet, R.; Bettler, M.O.; van Beuzekom, M.; Bien, A.; Bifani, S.; Bizzeti, A.; Bjornstad, P.M.; Blake, T.; Blanc, F.; Blanks, C.; Blouw, J.; Blusk, S.; Bobrov, A.; Bocci, V.; Bondar, A.; Bondar, N.; Bonivento, W.; Borghi, S.; Borgia, A.; Bowcock, T.J.V.; Bozzi, C.; Brambach, T.; van den Brand, J.; Bressieux, J.; Brett, D.; Brisbane, S.; Britsch, M.; Britton, T.; Brook, N.H.; Brown, H.; Buchler-Germann, A.; Burducea, I.; Bursche, A.; Buytaert, J.; Cadeddu, S.; Caicedo Carvajal, J.M.; Callot, O.; Calvi, M.; Calvo Gomez, M.; Camboni, A.; Campana, P.; Carbone, A.; Carboni, G.; Cardinale, R.; Cardini, A.; Carson, L.; Carvalho Akiba, K.; Casse, G.; Cattaneo, M.; Charles, M.; Charpentier, Ph.; Chiapolini, N.; Ciba, K.; Cid Vidal, X.; Ciezarek, G.; Clarke, P.E.L.; Clemencic, M.; Cliff, H.V.; Closier, J.; Coca, C.; Coco, V.; Cogan, J.; Collins, P.; Constantin, F.; Conti, G.; Contu, A.; Cook, A.; Coombes, M.; Corti, G.; Cowan, G.A.; Currie, R.; D'Almagne, B.; D'Ambrosio, C.; David, P.; De Bonis, I.; De Capua, S.; De Cian, M.; De Lorenzi, F.; de Miranda, J.M.; De Paula, L.; De Simone, P.; Decamp, D.; Deckenhoff, M.; Degaudenzi, H.; Deissenroth, M.; Del Buono, L.; Deplano, C.; Deschamps, O.; Dettori, F.; Dickens, J.; Dijkstra, H.; Diniz Batista, P.; Donleavy, S.; Dosil Suarez, A.; Dossett, D.; Dovbnya, A.; Dupertuis, F.; Dzhelyadin, R.; Eames, C.; Easo, S.; Egede, U.; Egorychev, V.; Eidelman, S.; van Eijk, D.; Eisele, F.; Eisenhardt, S.; Ekelhof, R.; Eklund, L.; Elsasser, Ch.; d'Enterria, D.G.; Esperante Pereira, D.; Esteve, L.; Falabella, A.; Fanchini, E.; Farber, C.; Fardell, G.; Farinelli, C.; Farry, S.; Fave, V.; Fernandez Albor, V.; Ferro-Luzzi, M.; Filippov, S.; Fitzpatrick, C.; Fontana, M.; Fontanelli, F.; Forty, R.; Frank, M.; Frei, C.; Frosini, M.; Furcas, S.; Gallas Torreira, A.; Galli, D.; Gandelman, M.; Gandini, P.; Gao, Y.; Garnier, J-C.; Garofoli, J.; Garra Tico, J.; Garrido, L.; Gaspar, C.; Gauvin, N.; Gersabeck, M.; Gershon, T.; Ghez, Ph.; Gibson, V.; Gligorov, V.V.; Gobel, C.; Golubkov, D.; Golutvin, A.; Gomes, A.; Gordon, H.; Grabalosa Gandara, M.; Graciani Diaz, R.; Granado Cardoso, L.A.; Grauges, E.; Graziani, G.; Grecu, A.; Gregson, S.; Gui, B.; Gushchin, E.; Guz, Yu.; Gys, T.; Haefeli, G.; Haen, C.; Haines, S.C.; Hampson, T.; Hansmann-Menzemer, S.; Harji, R.; Harnew, N.; Harrison, J.; Harrison, P.F.; He, J.; Heijne, V.; Hennessy, K.; Henrard, P.; Hernando Morata, J.A.; van Herwijnen, E.; Hicks, E.; Hofmann, W.; Holubyev, K.; Hopchev, P.; Hulsbergen, W.; Hunt, P.; Huse, T.; Huston, R.S.; Hutchcroft, D.; Hynds, D.; Iakovenko, V.; Ilten, P.; Imong, J.; Jacobsson, R.; Jaeger, A.; Jahjah Hussein, M.; Jans, E.; Jansen, F.; Jaton, P.; Jean-Marie, B.; Jing, F.; John, M.; Johnson, D.; Jones, C.R.; Jost, B.; Kandybei, S.; Karacson, M.; Karbach, T.M.; Keaveney, J.; Kerzel, U.; Ketel, T.; Keune, A.; Khanji, B.; Kim, Y.M.; Knecht, M.; Koblitz, S.; Koppenburg, P.; Kozlinskiy, A.; Kravchuk, L.; Kreplin, K.; Kreps, M.; Krocker, G.; Krokovny, P.; Kruse, F.; Kruzelecki, K.; Kucharczyk, M.; Kukulak, S.; Kumar, R.; Kvaratskheliya, T.; La Thi, V.N.; Lacarrere, D.; Lafferty, G.; Lai, A.; Lambert, D.; Lambert, R.W.; Lanciotti, E.; Lanfranchi, G.; Langenbruch, C.; Latham, T.; Le Gac, R.; van Leerdam, J.; Lees, J.P.; Lefevre, R.; Leflat, A.; Lefrancois, J.; Leroy, O.; Lesiak, T.; Li, L.; Li Gioi, L.; Lieng, M.; Liles, M.; Lindner, R.; Linn, C.; Liu, B.; Liu, G.; Lopes, J.H.; Lopez Asamar, E.; Lopez-March, N.; Luisier, J.; Machefert, F.; Machikhiliyan, I.V.; Maciuc, F.; Maev, O.; Magnin, J.; Malde, S.; Mamunur, R.M.D.; Manca, G.; Mancinelli, G.; Mangiafave, N.; Marconi, U.; Marki, R.; Marks, J.; Martellotti, G.; Martens, A.; Martin, L.; Martin Sanchez, A.; Martinez Santos, D.; Massafferri, A.; Mathe, Z.; Matteuzzi, C.; Matveev, M.; Maurice, E.; Maynard, B.; Mazurov, A.; McGregor, G.; McNulty, R.; Mclean, C.; Meissner, M.; Merk, M.; Merkel, J.; Messi, R.; Miglioranzi, S.; Milanes, D.A.; Minard, M.N.; Monteil, S.; Moran, D.; Morawski, P.; Mountain, R.; Mous, I.; Muheim, F.; Muller, K.; Muresan, R.; Muryn, B.; Musy, M.; Mylroie-Smith, J.; Naik, P.; Nakada, T.; Nandakumar, R.; Nardulli, J.; Nasteva, I.; Nedos, M.; Needham, M.; Neufeld, N.; Nguyen-Mau, C.; Nicol, M.; Nies, S.; Niess, V.; Nikitin, N.; Oblakowska-Mucha, A.; Obraztsov, V.; Oggero, S.; Ogilvy, S.; Okhrimenko, O.; Oldeman, R.; Orlandea, M.; Otalora Goicochea, J.M.; Owen, P.; Pal, B.; Palacios, J.; Palutan, M.; Panman, J.; Papanestis, A.; Pappagallo, M.; Parkes, C.; Parkinson, C.J.; Passaleva, G.; Patel, G.D.; Patel, M.; Paterson, S.K.; Patrick, G.N.; Patrignani, C.; Pavel-Nicorescu, C.; Pazos Alvarez, A.; Pellegrino, A.; Penso, G.; Pepe Altarelli, M.; Perazzini, S.; Perego, D.L.; Perez Trigo, E.; Perez-Calero Yzquierdo, A.; Perret, P.; Perrin-Terrin, M.; Pessina, G.; Petrella, A.; Petrolini, A.; Pie Valls, B.; Pietrzyk, B.; Pilar, T.; Pinci, D.; Plackett, R.; Playfer, S.; Plo Casasus, M.; Polok, G.; Poluektov, A.; Polycarpo, E.; Popov, D.; Popovici, B.; Potterat, C.; Powell, A.; du Pree, T.; Prisciandaro, J.; Pugatch, V.; Puig Navarro, A.; Qian, W.; Rademacker, J.H.; Rakotomiaramanana, B.; Rangel, M.S.; Raniuk, I.; Raven, G.; Redford, S.; Reid, M.M.; dos Reis, A.C.; Ricciardi, S.; Rinnert, K.; Roa Romero, D.A.; Robbe, P.; Rodrigues, E.; Rodrigues, F.; Rodriguez Perez, P.; Rogers, G.J.; Roiser, S.; Romanovsky, V.; Rouvinet, J.; Ruf, T.; Ruiz, H.; Sabatino, G.; Saborido Silva, J.J.; Sagidova, N.; Sail, P.; Saitta, B.; Salzmann, C.; Sannino, M.; Santacesaria, R.; Santinelli, R.; Santovetti, E.; Sapunov, M.; Sarti, A.; Satriano, C.; Satta, A.; Savrie, M.; Savrina, D.; Schaack, P.; Schiller, M.; Schleich, S.; Schmelling, M.; Schmidt, B.; Schneider, O.; Schopper, A.; Schune, M.H.; Schwemmer, R.; Sciubba, A.; Seco, M.; Semennikov, A.; Senderowska, K.; Sepp, I.; Serra, N.; Serrano, J.; Seyfert, P.; Shao, B.; Shapkin, M.; Shapoval, I.; Shatalov, P.; Shcheglov, Y.; Shears, T.; Shekhtman, L.; Shevchenko, O.; Shevchenko, V.; Shires, A.; Coutinho, R.Silva; Skottowe, H.P.; Skwarnicki, T.; Smith, A.C.; Smith, N.A.; Sobczak, K.; Soler, F.J.P.; Solomin, A.; Soomro, F.; Souza De Paula, B.; Spaan, B.; Sparkes, A.; Spradlin, P.; Stagni, F.; Stahl, S.; Steinkamp, O.; Stoica, S.; Stone, S.; Storaci, B.; Straticiuc, M.; Straumann, U.; Styles, N.; Subbiah, V.K.; Swientek, S.; Szczekowski, M.; Szczypka, P.; Szumlak, T.; T'Jampens, S.; Teodorescu, E.; Teubert, F.; Thomas, C.; Thomas, E.; van Tilburg, J.; Tisserand, V.; Tobin, M.; Topp-Joergensen, S.; Tran, M.T.; Tsaregorodtsev, A.; Tuning, N.; Ukleja, A.; Urquijo, P.; Uwer, U.; Vagnoni, V.; Valenti, G.; Vazquez Gomez, R.; Vazquez Regueiro, P.; Vecchi, S.; Velthuis, J.J.; Veltri, M.; Vervink, K.; Viaud, B.; Videau, I.; Vilasis-Cardona, X.; Visniakov, J.; Vollhardt, A.; Voong, D.; Vorobyev, A.; Voss, H.; Wacker, K.; Wandernoth, S.; Wang, J.; Ward, D.R.; Webber, A.D.; Websdale, D.; Whitehead, M.; Wiedner, D.; Wiggers, L.; Wilkinson, G.; Williams, M.P.; Williams, M.; Wilson, F.F.; Wishahi, J.; Witek, M.; Witzeling, W.; Wotton, S.A.; Wyllie, K.; Xie, Y.; Xing, F.; Yang, Z.; Young, R.; Yushchenko, O.; Zavertyaev, M.; Zhang, L.; Zhang, W.C.; Zhang, Y.; Zhelezov, A.; Zhong, L.; Zverev, E.; Zvyagin, A.

    2012-01-01

    The $B^0_s$-$\\overline{B}^0_s$ oscillation frequency $\\Delta m_s$ is measured with 36 pb$^{-1}$ of data collected in $pp$ collisions at $\\sqrt{s}$ = 7 TeV by the LHCb experiment at the Large Hadron Collider. A total of 1381 $B^0_s \\rightarrow D_s^- \\pi^+$ and $B^0_s \\rightarrow D_s^- \\pi^+\\pi^-\\pi^+$ signal decays are reconstructed, with average decay time resolutions of 44~fs and 36~fs, respectively. An oscillation signal with a statistical significance of 4.6\\,$\\sigma$ is observed. The measured oscillation frequency is $\\Delta m_s$ = 17.63 $\\pm$ 0.11 (stat) $\\pm$ 0.02 (syst)~ps$^{-1}$.

  14. Design and construction of a preamplifier for research reactor control system using Russia’s neutron detectors

    International Nuclear Information System (INIS)

    Trinh Dinh Hai; Vo Van Tai; Le Van Diep; Nguyen Nhi Dien

    2016-01-01

    This paper presents the design and construction of a preamplifier device for Research Reactor Control System, using Russia’s Neutron Detectors of ionization and fission chambers. In this work, the preamplifier device which consists of a wide range Current to Frequency Converter block used with a compensation ionization chamber type KNK-3 to measure the thermal neutron flux in the range of 1x10"6 - 1x10"1"1 n/cm"2.s, a Pulse Preamplifier block used with a fission chamber type KNK-15 to measure the thermal neutron flux in the range of 1x10"0 - 1x10"6 n/cm"2.s, and a Power Supply block, was designed and tested in different conditions in the laboratory and at Dalat Nuclear Research Reactor (DNRR). Obtained results show that, the above blocks have almost design specifications as equivalent or better in comparison with the same function blocks of the DNRR Control System which were designed by the former Soviet Union. They also meet the utilization requirements as well as the experimental and training purposes. (author)

  15. JENDL-3.3 thermal reactor benchmark test

    International Nuclear Information System (INIS)

    Akie, Hiroshi

    2001-01-01

    Integral tests of JENDL-3.2 nuclear data library have been carried out by Reactor Integral Test WG of Japanese Nuclear Data Committee. The most important problem in the thermal reactor benchmark testing was the overestimation of the multiplication factor of the U fueled cores. With several revisions of the data of 235 U and the other nuclides, JENDL-3.3 data library gives a good estimation of multiplication factors both for U and Pu fueled thermal reactors. (author)

  16. Recent U.S. reactor operating experience

    International Nuclear Information System (INIS)

    Stello, V. Jr.

    1977-01-01

    A qualitative assessment of U.S. and foreign reactor operating experience is provided. Recent operating occurrences having potentially significant safety impacts on power operation are described. An evaluation of the seriousness of each of these issues and the plans for resolution is discussed. A quantitative report on U.S. reactor operational experience is included. The details of the NRC program for evaluating and applying operating reactor experience in the regulatory process is discussed. A review is made of the adequacy of operating reactor safety and environmental margins based on actual operating experience. The Regulatory response philosophy to operating reactor experiences is detailed. This discussion indicates the NRC emphasis on the importance of a balanced action plan to provide for the protection of public safety in the national interest

  17. Nielsen: Aladdin-Suite, FS89. Maskarade-Overture / Robert Layton

    Index Scriptorium Estoniae

    Layton, Robert

    1996-01-01

    Uuest heliplaadist "Nielsen: Aladdin-Suite, FS89. Maskarade-Overture, Prelude, Act 2. The Cockerels' Dance. Rhapsody Overture: An imaginary journey to the Faroe Islands, FS123. Helios Overture, FS32. Saga-Drom, FS46. Pan and Syrinx, FS87. Gothenburg Symphony Orchestra, Neeme Järvi" DG 447 757-2GH (72 minutes: DDD)

  18. (2S,7S-10-Ethyl-1,8,10,12-tetraazatetracyclo[8.3.1.18,12.02,7]pentadecan-10-ium iodide

    Directory of Open Access Journals (Sweden)

    Augusto Rivera

    2012-10-01

    Full Text Available The title chiral quaternary ammonium salt, C13H25N4+·I−, was synthesized through the Menschutkin reaction between the cage aminal (2S,7S-1,8,10,12-tetraazatetracyclo[8.3.1.18,12.02,7]pentadecane and ethyl iodide. The quaternization occurred regioselectively on the nitrogen with major sp3 character. The crystal structure consists of anions and cations separated by normal distances. Ions are not linked through C—H...I hydrogen bonds.

  19. Course of operators of the RA-3 reactor

    International Nuclear Information System (INIS)

    Caligiuri, G.A.

    1983-01-01

    Description of the fundamental principles of the nuclear reactors' control systems. The RA-3 reactor's control and measurement systems are principally described, without setting aside the basic criteria for the design of an appropriate instrumentation for the control of a nuclear reactor, as well as the theory on which the functioning of the several detectors and equipments used in a nuclear instrumentation are based. The main purpose of this course is that of serving, preferentially as a text, for the training of personnel which shall perform operation tasks in this reactor. The work includes three well-defined sections. The first two ones make an introduction to the subject, while the third one, extending to more than half-work, deals with the general description of the system in which the control and operation logic of RA-3 are included. (R.J.S) [es

  20. Submersion-Subcritical Safe Space (S4) reactor

    International Nuclear Information System (INIS)

    King, Jeffrey C.; El-Genk, Mohamed S.

    2006-01-01

    The Submersion-Subcritical Safe Space (S 4 ) reactor, developed for future space power applications and avoidance of single point failures, is presented. The S 4 reactor has a Mo-14% Re solid core, loaded with uranium nitride fuel, cooled by He-30% Xe and sized to provide 550 kWth for 7 years of equivalent full power operation. The beryllium oxide reflector of the S 4 reactor is designed to completely disassemble upon impact on water or soil. The potential of using Spectral Shift Absorber (SSA) materials in different forms to ensure that the reactor remains subcritical in the worst-case submersion accident is investigated. Nine potential SSAs are considered in terms of their effect on the thickness of the radial reflector and on the combined mass of the reactor and the radiation shadow shield. The SSA materials are incorporated as a thin (0.1 mm) coating on the outside surface of the reactor core and as core additions in three possible forms: 2.0 mm diameter pins in the interstices of the core block, 0.25 mm thick sleeves around the fuel stacks and/or additions to the uranium nitride fuel. Results show that with a boron carbide coating and 0.25 mm iridium sleeves around the fuel stacks the S 4 reactor has a reflector outer diameter of 43.5 cm with a combined reactor and shadow shield mass of 935.1 kg. The S 4 reactor with 12.5 at.% gadolinium-155 added to the fuel, 2.0 mm diameter gadolinium-155 sesquioxide interstitial pins, and a 0.1 mm thick gadolinium-155 sesquioxide coating has a slightly smaller reflector outer diameter of 43.0 cm, resulting in a smaller total reactor and shield mass of 901.7 kg. With 8.0 at.% europium-151 added to the fuel, along with europium-151 sesquioxide for the pins and coating, the reflector's outer diameter and the total reactor and shield mass are further reduced to 41.5 cm and 869.2 kg, respectively

  1. FS laser processing of bio-polymer thin films for studying cell-to-substrate specific response

    Energy Technology Data Exchange (ETDEWEB)

    Daskalova, A., E-mail: a_daskalova@code.bg [Institute of Electronics, Bulgarian Academy of Sciences, 72, Tsarigradsko Chaussee Blvd., 1784 Sofia (Bulgaria); Nathala, Chandra S.R. [Institute of General Physics, Vienna University of Technology, Wiedner Hauptstr. 8-10/134, A-1040 Wien (Austria); Spectra-Physics Vienna, Fernkorngasse 10, 1100 Wien (Austria); Kavatzikidou, P.; Ranella, A. [Institute for Electronic Structure and Lasers-FORTH, P.O. Box 1385, Vassilika Vouton, 711 10 Heraklion, Crete (Greece); Szoszkiewicz, R. [Faculty of Materials Science and Engineering, Warsaw University of Technology, 141 Woloska Str., 02-507 Warsaw, Poland (Poland); Husinsky, W. [Institute of General Physics, Vienna University of Technology, Wiedner Hauptstr. 8-10/134, A-1040 Wien (Austria); Fotakis, C. [Institute for Electronic Structure and Lasers-FORTH, P.O. Box 1385, Vassilika Vouton, 711 10 Heraklion, Crete (Greece)

    2016-09-30

    Highlights: • Systematic research in the field of fs laser interaction with biopolymers for application in tissue engineering. • Utilizing a new biopolymer blend of collagen/elastin material for studying the interaction process in the fs domain. • Obtaining of improved, circularly shaped, interconnected nanopores, with high reproducibility from collagen/elastin layer. • Observation of randomly arranged pattern outside modification zone due to formation of an impact wave over biofilm surface. • NIH/3T3 cell-interface interaction reveal a preferable cell migration on fs laser-modified surface array. - Abstract: The use of ultra-short pulses for nanoengineering of biomaterials opens up possibilities for biological, medical and tissue engineering applications. Structuring the surface of a biomaterial into arrays with micro- and nanoscale features and architectures, defines new roadmaps to innovative engineering of materials. Thin films of novel collagen/elastin composite and gelatin were irradiated by Ti:sapphire fs laser in air at central wavelength 800 nm, with pulse durations in the range of 30 fs. The size and shape as well as morphological forms occurring in the resulted areas of interaction were analyzed as a function of irradiation fluence and number of pulses by atomic force microscopy (AFM). The fs interaction regime allows generation of well defined micro porous surface arrays. In this study we examined a novel composite consisting of collagen and elastin in order to create a biodegradable matrix to serve as a biomimetic surface for cell attachment. Confocal microscopy images of modified zones reveal formation of surface fringe patterns with orientation direction alongside the area of interaction. Outside the crater rim a wave-like topography pattern is observed. Structured, on a nanometer scale, surface array is employed for cell-culture experiments for testing cell’s responses to substrate morphology. Mice fibroblasts migration was monitored

  2. FS laser processing of bio-polymer thin films for studying cell-to-substrate specific response

    International Nuclear Information System (INIS)

    Daskalova, A.; Nathala, Chandra S.R.; Kavatzikidou, P.; Ranella, A.; Szoszkiewicz, R.; Husinsky, W.; Fotakis, C.

    2016-01-01

    Highlights: • Systematic research in the field of fs laser interaction with biopolymers for application in tissue engineering. • Utilizing a new biopolymer blend of collagen/elastin material for studying the interaction process in the fs domain. • Obtaining of improved, circularly shaped, interconnected nanopores, with high reproducibility from collagen/elastin layer. • Observation of randomly arranged pattern outside modification zone due to formation of an impact wave over biofilm surface. • NIH/3T3 cell-interface interaction reveal a preferable cell migration on fs laser-modified surface array. - Abstract: The use of ultra-short pulses for nanoengineering of biomaterials opens up possibilities for biological, medical and tissue engineering applications. Structuring the surface of a biomaterial into arrays with micro- and nanoscale features and architectures, defines new roadmaps to innovative engineering of materials. Thin films of novel collagen/elastin composite and gelatin were irradiated by Ti:sapphire fs laser in air at central wavelength 800 nm, with pulse durations in the range of 30 fs. The size and shape as well as morphological forms occurring in the resulted areas of interaction were analyzed as a function of irradiation fluence and number of pulses by atomic force microscopy (AFM). The fs interaction regime allows generation of well defined micro porous surface arrays. In this study we examined a novel composite consisting of collagen and elastin in order to create a biodegradable matrix to serve as a biomimetic surface for cell attachment. Confocal microscopy images of modified zones reveal formation of surface fringe patterns with orientation direction alongside the area of interaction. Outside the crater rim a wave-like topography pattern is observed. Structured, on a nanometer scale, surface array is employed for cell-culture experiments for testing cell’s responses to substrate morphology. Mice fibroblasts migration was monitored

  3. Qualification of the Taiwan Power Company's pressurized water reactor physics methods using CASMO-4/SIMULATE-3

    Energy Technology Data Exchange (ETDEWEB)

    Lin, Hsien-Chuan, E-mail: linsc@iner.org.tw [Nuclear Engineering Division, Institute of Nuclear Energy Research, 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China); Yaur, Shung-Jung; Lin, Tzung-Yi; Kuo, Weng-Sheng; Shiue, Jin-Yih; Huang, Yu-Lung [Nuclear Engineering Division, Institute of Nuclear Energy Research, 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China)

    2012-12-15

    Highlights: Black-Right-Pointing-Pointer Studsvik's core management system (CMS) was applied to Taiwan Power Company's pressurized water reactor. Black-Right-Pointing-Pointer Advanced calculation model of shutdown cooling, B-10 depletion and integrated pin exposure were introduced. Black-Right-Pointing-Pointer Core characteristic parameters such as boron letdown, low power physics test (LPPT) predictions, and reaction rate were validated to measurement data. Black-Right-Pointing-Pointer The uncertainty of each item was quantified. - Abstract: This paper presents the validation of Studsvik core management system (CMS) for application to the Maanshan units 1 and 2 reactor core physics analysis (Huang and Yang, 1994). The methodology was validated by demonstrating the ability to obtain accurate and reliable results for various conditions and applications. Core characteristic parameters such as boron letdown, low power physics test (LPPT) predictions, and reaction rate were validated. Analytical results have been compared to measured data and reliability factors of the method have been quantified.

  4. SeaWiFS_L3m_MO_CHL_chlor_a_9km

    Data.gov (United States)

    National Aeronautics and Space Administration — The SeaWiFS instrument was launched by Orbital Sciences Corporation on the OrbView-2 (a.k.a. SeaStar) satellite in August 1997, and collected data from September...

  5. Radiological protection of the staff during the decommissioning operations of the Romanian VVR-S research reactor

    International Nuclear Information System (INIS)

    Ene, D.C.

    2002-01-01

    Dose rate estimates for periods of 100 days and 6, 10, 25, 100 years after the shut down of the Romanian VVR-S reactor are presented in this paper for some foreseen decommissioning activities which include: i) cutting the water pipe in the pump room and the reactor sealing operations; ii) extracting reactor components; and iii) handling and dismantling the internal structures taken of from the reactor. For the reactor components extracted from the reactor, the considered calculation points were placed in the central plan of the items, on the surface and at distances from the surface which correspond to +0.2m, +1m, +2m, +8m, and +10m. Time dependence of the resulted dose rates are presented and discussed. Qualitative comparison with the measured values from other VVR-S reactors is done. The obtained results assist to develop working procedures that must be observed during the decommissioning activities. (author)

  6. Fuel cladding mechanical properties for transient analysis

    International Nuclear Information System (INIS)

    Johnson, G.D.; Hunter, C.W.; Hanson, J.E.

    1976-01-01

    Out-of-pile simulated transient tests have been conducted on irradiated fast-reactor fuel pin cladding specimens at heating rates of 10 0 F/s (5.6 0 K/s) and 200 0 F/s (111 0 K/s) to generate mechanical property information for use in describing cladding behavior during off-normal events. Mechanical property data were then analyzed, applying the Larson-Miller Parameter to the effects of heating rate and neutron fluence. Data from simulated transient tests on TREAT-tested fuel pins demonstrate that Plant Protective System termination of 3$/s transients prevents significant damage to cladding. The breach opening produced during simulated transient testing is shown to decrease in size with increasing neutron fluence

  7. Generation of 70-fs pulses at 286 μm from a mid-infrared fiber laser

    Science.gov (United States)

    Woodward, R. I.; Hudson, D. D.; Fuerbach, A.; Jackson, S. D.

    2017-12-01

    We propose and demonstrate a simple route to few-optical-cycle pulse generation from a mid-infrared fiber laser through nonlinear compression of pulses from a holmium-doped fiber oscillator using a short length of chalcogenide fiber and a grating pair. Pulses from the oscillator with 265-fs duration at 2.86 {\\mu}m are spectrally broadened through self-phase modulation in step-index As2S3 fiber to 141-nm bandwidth and then re-compressed to 70 fs (7.3 optical cycles). These are the shortest pulses from a mid-infrared fiber system to date, and we note that our system is compact, robust, and uses only commercially available components. The scalability of this approach is also discussed, supported by numerical modeling.

  8. SeaWiFS Third Anniversary Global Biosphere

    Science.gov (United States)

    2002-01-01

    September 18,2000 is the third anniversary of the start of regular SeaWiFS operations of this remarkable planet called Earth. This SeaWiFS image is of the Global Biosphere depicting the ocean's long-term average phytoplankton chlorophyll concentration acquired between September 1997 and August 2000 combined with the SeaWiFS-derived Normalized Difference Vegetation Index (NDVI) over land during July 2000.

  9. Root colonization and growth promotion of sunflower (Helianthus annuus L.) by phosphate solubilizing Enterobacter sp. Fs-11.

    Science.gov (United States)

    Shahid, Muhammad; Hameed, Sohail; Imran, Asma; Ali, Saira; van Elsas, Jan Dirk

    2012-08-01

    An Enterobacter sp. Fs-11 was isolated from sunflower rhizosphere, identified on the basis of 16S rRNA gene sequence analysis (GeneBank accession no. GQ179978) and studied for its root colonization and growth promotion ability in sunflower. Morphologically, it was rod shaped Gram-negative, motile bacterium, producing 4.5 μg mL(-1) indole acetic acid in tryptophan-supplemented medium. It utilized 27 out of 95 substrates in BIOLOG GN2 micro plate system. It was able to convert insoluble tri-calcium phosphate to soluble phosphorus up to 43.5 μg mL(-1) with decrease in pH of the medium up to 4.5 after 10 days incubation at 28 ± 2 °C in the Pikovskaya's broth. High performance liquid chromatography of cell free supernatant showed that Fs-11 produced malic acid and gluconic acid (2.43 and 16.64 μg mL(-1), respectively) in Pikovskaya's broth. Analysis of 900 bp fragment of pyrroloquinoline quinine pqqE gene sequence showed 98 % homology with that of E. cloacae pqqE gene. Confocal laser scanning microscope revealed strong colonization of fluorescently labeled Fs-11 with sunflower roots. Sunflower inoculation with Fs-11 and its rifampicin resistant derivative in sterile sand and natural soil showed that Fs-11 colonized sunflower roots up to 30 days after transplanting in both sterile sand as well as natural soil. Moreover, Fs-11 inoculation resulted in increased plant height, fresh weight, dry weight and total phosphorus contents as compared to un-inoculated plants. The data showed that Enterobacter sp. Fs-11 is an efficient phosphate solubilizing and plant growth promoting rhizobacterium and has great potential to be used as bio-inoculant for sunflower under phosphorus deficient conditions.

  10. Crystal structure of (1S,3R,8R,10S-2,2-dichloro-10-hydroxy-3,7,7,10-tetramethyltricyclo[6.4.0.01,3]dodecan-9-one

    Directory of Open Access Journals (Sweden)

    Ahmed Benzalim

    2016-05-01

    Full Text Available The asymmetric unit of the title compound, C16H24Cl2O2, contains two independent molecules (A and B which are built from three fused rings, viz. a seven-membered heptane ring, a six-membered cyclohexyl ring bearing a ketone and an alcohol group, and a cyclopropane ring bearing two Cl atoms. In the crystal, the two molecules are linked via two O—H...O hydrogen bonds, forming an A–B dimer with an R22(10 ring motif. The A molecules of these dimers are linked via a C—H...O hydrogen bond, forming chains propagating along the a-axis direction. Both molecules have the same absolute configuration, i.e. 1S,3R,8R,10S, which is based on the synthetic pathway and further confirmed by resonant scattering [Flack parameter = 0.03 (5].

  11. SeaWiFS: North Pacific Storm

    Science.gov (United States)

    2002-01-01

    An extratropical storm can be seen swirling over the North Pacific just south of Alaska. This SeaWiFS image was collected yesterday at 23:20 GMT. Credit: Provided by the SeaWiFS Project, NASA/Goddard Space Flight Center, and ORBIMAGE

  12. H. B. Robinson Plant, Unit 2. Semiannual operating report No. 10, January--June 1975

    International Nuclear Information System (INIS)

    1975-01-01

    Net electrical power generated was 2,051,619 MWH(e) with the reactor on line 3,063.39 hrs. Information is presented concerning power generation, shutdowns, corrective maintenance, chemistry and radiochemistry, occupational radiation exposure, release of radioactive materials, and abnormal occurrences. (FS)

  13. MANHATTAN PROJECT B REACTOR HANFORD WASHINGTON [HANFORD'S HISTORIC B REACTOR (12-PAGE BOOKLET)

    Energy Technology Data Exchange (ETDEWEB)

    GERBER MS

    2009-04-28

    The Hanford Site began as part of the United States Manhattan Project to research, test and build atomic weapons during World War II. The original 670-square mile Hanford Site, then known as the Hanford Engineer Works, was the last of three top-secret sites constructed in order to produce enriched uranium and plutonium for the world's first nuclear weapons. B Reactor, located about 45 miles northwest of Richland, Washington, is the world's first full-scale nuclear reactor. Not only was B Reactor a first-of-a-kind engineering structure, it was built and fully functional in just 11 months. Eventually, the shoreline of the Columbia River in southeastern Washington State held nine nuclear reactors at the height of Hanford's nuclear defense production during the Cold War era. The B Reactor was shut down in 1968. During the 1980's, the U.S. Department of Energy began removing B Reactor's support facilities. The reactor building, the river pumphouse and the reactor stack are the only facilities that remain. Today, the U.S. Department of Energy (DOE) Richland Operations Office offers escorted public access to B Reactor along a designated tour route. The National Park Service (NPS) is studying preservation and interpretation options for sites associated with the Manhattan Project. A draft is expected in summer 2009. A final report will recommend whether the B Reactor, along with other Manhattan Project facilities, should be preserved, and if so, what roles the DOE, the NPS and community partners will play in preservation and public education. In August 2008, the DOE announced plans to open B Reactor for additional public tours. Potential hazards still exist within the building. However, the approved tour route is safe for visitors and workers. DOE may open additional areas once it can assure public safety by mitigating hazards.

  14. Human factors engineering evaluation of the UTR-10 Reactor

    International Nuclear Information System (INIS)

    Lahti, D.; Nilius, D.; Heithoff, D.; Roche, G.; Sage, S.

    1982-01-01

    This paper is a description of a student design team's review and evaluation of Iowa State University's University Test Reactor (UTR-10). The review was based on how well the control room of the UTR-10 measured up to selected portions of NUREG-0800, chapter 18, Human Factor Engineering/Standard Review Plan Development. The review was conducted by inspecting the reactor and interviewing reactor operators. The control room workspace, instrumentation controls and other equipment were evaluated from a human factors engineering point of view that takes into account both system demands and operator capabilities. Identification, assessment, and suggestion for control room design modifications that correct inadequate or unsuitable items was made

  15. Dynamics of TRIGA-3 Salazar Reactor

    International Nuclear Information System (INIS)

    Gallardo S, L.F.

    1990-01-01

    The theoretical study of temporal behavior of a nuclear reactor is of great importance, since it allows to know, in advance, the conditions to which a reactor is going to be submitted. The reliability of two computer codes (AIREK-JEN and PLANKIN) designed to reproduce the temporal behavior of nuclear reactors, generally power reactors, when they are applied to reproduce the dynamic behavior of TRIGA-3 Salazar Reactor is analyzed. In the first chapters, the fundamental equations that solve this computer codes are deduced, and also the main characteristics of TRIGA-3 Salazar Reactor and the necessary data to run the programs are presented; later the results obtained with the computer codes and the experimental results reported in the operational logbook of the reactor are compared, with the result that such computer codes are applicable to the temporal study of TRIGA-3 Salazar Reactor. (Author)

  16. Determination of neutron flux densities in WWR-S reactor core

    International Nuclear Information System (INIS)

    Tomasek, F.

    1989-04-01

    The method is described of determining neutron flux densities and neutron fluences using activation detectors. The basic definitions and relations for determining reaction rates, fluence and neutron flux as well as the characteristics of some reactions and of sitable activation detectors are reported. The flux densities were determined of thermal and fast neutrons and of gamma quanta in the WWR-S reactor core. The data measured in the period 1984-1987 are tabulated. Cross sections for the individual reactions were determined from spectra measurements processed using program SAND-II and cross section library ENDF-B IV. Neutron flux densities were also measured for the WWR-S reactor vertical channels. (E.J.). 10 figs., 8 tabs., 111 refs

  17. LHCb: Measurement of the relative yields of the decay modes $B_{d,s} \\to D^{\\pm}_{(s)}\\pi^{\\mp}$ and $B_{d,s} \\to D^{\\pm}_{(s)} K^{\\pm}$ and determination of $f_d /f_s$ for 7 TeV $pp$ collisions

    CERN Multimedia

    David, P; Morawski, P; Witek, M; Akiba, K; Serra, N; Storaci, B; Tuning, N; Williams, M; Easo, S; Carson, L; Poluektov, A

    2011-01-01

    A fit to the invariant mass distributions is used to determine the relative abundances of the four decay modes $B_{d,s} \\to D^{\\pm}_{(s)}\\pi^{\\mp}$ and $B_{d,s} \\to D^{\\pm}_{(s)} K^{\\mp}$ for $B_{d,s}$ mesons produced in 7 TeV $pp$ collisions at the LHC. From these, the relative branching fractions of the kaon modes with respect to the pion modes, and the value of $f_d /f_s$, are determined.

  18. Dry Eye Disease following Refractive Surgery: A 12-Month Follow-Up of SMILE versus FS-LASIK in High Myopia

    Directory of Open Access Journals (Sweden)

    Bingjie Wang

    2015-01-01

    Full Text Available Purpose. To compare dry eye disease following SMILE versus FS-LASIK. Design. Prospective, nonrandomised, observational study. Patients. 90 patients undergoing refractive surgery for myopia were included. 47 eyes underwent SMILE and 43 eyes underwent FS-LASIK. Methods. Evaluation of dry eye disease was conducted preoperatively and at 1, 3, 6, and 12 months postoperatively, using the Salisbury Eye Evaluation Questionnaire (SEEQ and TBUT. Results. TBUT reduced following SMILE at 1 and 3 months (p<0.001 and at 1, 3, and 6 months following FS-LASIK (p<0.001. TBUT was greater following SMILE than FS-LASIK at 3, 6, and 12 months (p<0.001, p<0.001, and p=0.009, resp.. SEEQ scores increased (greater symptoms following SMILE at 1 month (p<0.001 and 3 months (p=0.003 and at 1, 3, and 6 months following FS-LASIK (p<0.001. SMILE produced lower SEEQ scores (fewer symptoms than FS-LASIK at 1, 3, and 6 months (p<0.001. Conclusion. SMILE produces less dry eye disease than FS-LASIK at 6 months postoperatively but demonstrates similar degrees of dry eye disease at 12 months.

  19. EL3 reactor description and safety analysis report

    International Nuclear Information System (INIS)

    1969-02-01

    The EL-3 reactor is an experimental pile. Heterogenous type reactor, water moderated and cooled it uses slightly enriched uranium oxide as fuel (4.5 percent) distributed in vertical cells that constitute the core (the maximum number of cells is 99). It is conceived to function at a maximal thermal power of 20 MW. It supplies a maximum thermal neutron flux of 10 14 neutrons/cm 2 /sec. It has several experimental devices. The EL-3 reactor is surrounded by auxiliary circuits of fluids, in a sealed containment, slightly depressed. The primary heavy water coolant circuit is completely included in this containment. Its cooling is made by the intermediary of a light water secondary circuit by atmospheric refrigerants. The ventilation circuits of the sealed containment and the reactor block do not release air outside, under nornal functioning, by a particularly studied chimney only after filtering and eventually dilution. The eventual contamination of the light water or air by active products is permanently monitored to allow the reactor shutdown and avoid the release in atmosphere of dangerous products. The EL-3 reactor, laying down in may 1955, has diverged in july 1957, made its first ascending in power in december 1957 and reached its complete power in april 1958. The positioning of actual fuel (snow crystal) was made during summer 1964. Reactor with an experimental aim, it is used for theoretical and technological studies by material irradiation in the experimental channels and the core cells, with possibilities to constitute independent loops (relative to the cooling fluids). Thirty vertical channels are devoted to the fabrication of artificial radioelements [fr

  20. U.S. Nuclear Power Reactor Plant Status

    Data.gov (United States)

    Nuclear Regulatory Commission — Demographic data on U.S. commercial nuclear power reactors, including: plant name/unit number, docket number, location, licensee, reactor/containment type, nuclear...

  1. [Atmospheric emission of PCDD/Fs from secondary aluminum metallurgy industry in the southwest area, China].

    Science.gov (United States)

    Lu, Yi; Zhang, Xiao-Ling; Guo, Zhi-Shun; Jian, Chuan; Zhu, Ming-Ji; Deng, Li; Sun, Jing; Zhang, Qin

    2014-01-01

    Five secondary aluminum metallurgy enterprises in the southwest area of China were measured for emissions of PCDD/Fs. The results indicated that the emission levels of PCDD/Fs (as TEQ) were 0.015-0.16 ng x m(-3), and the average was 0.093 ng x m(-3) from secondary aluminum metallurgy enterprises. Emission factors of PCDD/Fs (as TEQ) from the five secondary aluminum metallurgy enterprises varied between 0.041 and 4.68 microg x t(-1) aluminum, and the average was 2.01 microg x t(-1) aluminum; among them, PCDD/Fs emission factors from the crucible smelting furnace was the highest. Congener distribution of PCDD/F in stack gas from the five secondary aluminum metallurgies was very different from each other. Moreover, the R(PCDF/PCDD) was the lowest in the enterprise which was installed only with bag filters; the R(PCDF/PCDD) were 3.8-12.6 (the average, 7.7) in the others which were installed with water scrubbers. The results above indicated that the mechanism of PCDD/Fs formation was related to the types of exhaust gas treatment device. The results of this study can provide technical support for the formulation of PCDD/Fs emission standards and the best available techniques in the secondary aluminum metallurgy industry.

  2. Safety demonstration test (SR-3/S1C-3/S2C-3/SF-2) plan using the HTTR. Contract research

    International Nuclear Information System (INIS)

    Nakagawa, Shigeaki; Sakaba, Nariaki; Takamatsu, Kuniyoshi; Takada, Eiji; Tochio, Daisuke; Ohwada, Hiroyuki

    2005-03-01

    Safety demonstration tests using the HTTR are to be conducted from the FY2002 to verify the inherent safety features and to improve the safety design and evaluation technologies for HTGRs, as well as to contribute to not only the commercial HTGRs but also the research and development for the VHTR that is one of the Generation IV reactor candidates. This paper describes the reactivity insertion test (SR-3), the coolant flow reduction test by tripping of gas circulators (S1C-3, S2C-3), and the partial flow loss of coolant test (SF-2) planned in March 2005 with their detailed test method, procedure and results of pre-test analysis. From the analytical results, it was verified that the negative reactivity feedback effect of the core brings the reactor power safely to a stable level without a reactor scram. (author)

  3. Current status of feasibility studies on commercialized fuel cycle system for Fast Breeder Reactor

    International Nuclear Information System (INIS)

    Ojima, Hisao; Nagaoki, Yoshihiro

    2000-01-01

    A 'Feasibility Studies on Commercialized Fast Breeder Reactor Cycle System' is underway at the Japan Nuclear Cycle Development Institute (JNC). The study will select the promising concepts with their R and D tasks in order to commercialize the fast breeder reactor (FBR) cycle system. The feasibility studies (F/S) have to present surveyed and screened various relevant technologies, and defined the design requirement of the commercialized fuel cycle system for FBR. The promising technical options are being evaluated and conceptual designs are being examined. At the end of JFY2000, several candidate concepts of the commercialized FBR cycle system will be proposed. (author)

  4. Characteristics of particle-bound polychlorinated dibenzo-p-dioxins and dibenzofurans (PCDD/Fs) in atmosphere used in carbon black feeding process at a tire manufacturing plant.

    Science.gov (United States)

    Chuang, Kuen-Yuan; Lai, Chia-Hsiang; Peng, Yen-Ping; Yen, Ting-Yu

    2015-12-01

    Concentrations of polychlorinated dibenzo-p-dioxins and dibenzofurans (PCDD/Fs) were estimated for different particle size distributions in a carbon black feeding process at a tire manufacturing plant on 15 days in March and April of 2014. A total of 75 integrated air samples were collected using a micro-orifice uniform deposition impactor (MOUDI). Particle-bound PCDD/Fs were analyzed using a high-resolution gas chromatograph/high-resolution mass spectrometer (HRGC/HRMS). Concentrations of thoracic particles and total particles produced in the carbon black feeding process of a tire manufacturing plant were measured in ranges of 0.19-2.61 and 0.28-4.22 mg/m(3), respectively. On all sampling days, the three most abundant species of PCDD/Fs were OCDD, 1,2,3,4,6,7,8-HpCDF, and OCDF. The mean concentrations of total PCDD/Fs were 0.74-6.83 pg/m(3) within five particle size ranges. Total I-TEQ in particulate matter (PM)18 and PM2.5-10, respectively. However, the total I-TEQ of thoracic PM contributed approximately 74 % of the total I-TEQ of total PM. The assessment of health risk indicates that exposure to fractions of thoracic PM by inhalation poses a significant cancer risk (>10(-6)).

  5. Femtosecond (FS) laser vision correction procedure for moderate to high myopia

    DEFF Research Database (Denmark)

    Vestergaard, Anders Højslet; Ivarsen, Anders; Asp, Sven

    2013-01-01

    Purpose:  To present our initial clinical experience with ReLEx(®) flex (ReLEx) for moderate to high myopia. We compare efficacy, safety and corneal higher-order aberrations after ReLEx with femtosecond laser in situ keratomileusis (FS-LASIK). Methods:  Prospective study of ReLEx compared...... with a retrospective study of FS-LASIK. ReLEx is a new keratorefractive procedure, where a stromal lenticule is cut by a femtosecond laser and manually extracted. Forty patients were treated with ReLEx on both eyes. A comparable group of 41 FS-LASIK patients were retrospectively identified. Visual acuity, spherical...... equivalent (SE) and corneal tomography were measured before and 3 months after surgery. Results:  Preoperative SE averaged -7.50 ± 1.16 D (ReLEx) and -7.32 ± 1.09 D (FS-LASIK). For all eyes, mean corrected distance visual acuity remained unchanged in both groups. For eyes with emmetropia as target refraction...

  6. Summary of IEA-R1 research a reactor licensing related to its power increase from 2 to 10 MW

    International Nuclear Information System (INIS)

    1989-04-01

    This work is a summary of IEA-R1 research reactor licensing related to its power increase from 2 to 10 MW. It reports also safety requirements, fuel elements, and reactor control modifications inherent to power increase. (A.C.A.S.)

  7. [Study on secondary metabolites of marine fungus Penicillium sp. FS60 from the South China Sea].

    Science.gov (United States)

    Zhang, Ling; Li, Dong-Li; Chen, Yu-Chan; Tao, Mei-Hua; Zhang, Wei-Min

    2012-07-01

    To study the secondary metabolites of the marine fungus Penicillium sp. FS60 from the South China Sea and their cytotoxicities. The compounds were isolated from the culture of strain FS60 by various chromatographic methods (silica gel, reverse silica gel, Sephadex-LH20, preparative TLC, HPLC and PTLC) and recrystallization. Their structures were identified by extensive analysis of their spectroscopic data. Compounds were tested for their cytotoxicities against SF-268, MCF-7, and NCI-H460 cell lines by SRB method. While, Compounds were tested for their antibacterial activities against S. aureus, E. coli and P. aeruginosa. Seven compounds were isolated from the culture and identified as methyl 2,4-dihydroxy-3,5,6-trimethylbenzoate (1), 4-hydroxyacetophenone (2), 5-hydroxymethyl-furoic acid (3), isochromophilones VIII (4), ergosterol (5), ergosterol peroxide (6), and cerevisterol (7). Compound 1 is isolated from the genus Penicillium for the first time. Compound 3 is demonstrated to have significant inhibition against S. aureus and P. aeruginosa. Compound 4 is demonstrated to have significant inhibition against the three cell lines.

  8. EST Table: FS920530 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS920530 E_FL_fufe_50K23_F_0 11/12/09 GO hit GO:0047800(cysteamine dioxygenase acti...090992|ref|XP_974899.1| PREDICTED: similar to 2-aminoethanethiol (cysteamine) dioxygenase [Tribolium castaneum] FS920530 fufe ...

  9. EST Table: FS737333 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS737333 E_FL_bmmt_08I09_R_0 10/09/28 68 %/182 aa ref|NP_059479.1| ATP synthase F0 ...subunit 6 [Bombyx mori] gb|AAF73768.1|AF149768_12 ATPase 6 [Bombyx mori] gb|AAK85722.1| ATPase subunit 6 [Bo....1| ATP synthase F0 subunit 6 [Bombyx mori] gb|ADE18460.1| ATP synthase F0 subunit 6 [Bombyx mori] gb|ADE18473

  10. Enthalpy increment measurements of Sr3Zr2O7(s) and Sr4Zr3O10(s)

    International Nuclear Information System (INIS)

    Banerjee, A.; Dash, S.; Prasad, R.; Venugopal, V.

    1998-01-01

    Enthalpy increment measurements on Sr 3 Zr 2 O 7 (s) and Sr 4 Zr 3 O 10 (s) were carried out using a Calvet micro-calorimeter. The enthalpy increment values were least squares analyzed with the constraints that H 0 (T)-H 0 (298.15 K) at 298.15 K equals to zero and C p 0 (298.15 K) equals to the estimated value. The dependence of enthalpy increment with temperature is given. (orig.)

  11. Advances in U.S. reactor physics standards

    International Nuclear Information System (INIS)

    Cokinos, Dimitrios

    2008-01-01

    The standards for Reactor Design, widely used in the nuclear industry, provide guidance and criteria for performing and validating a wide range of nuclear reactor calculations and measurements. Advances, over the past decades in reactor technology, nuclear data and infrastructure in the data handling field, led to major improvements in the development and application of reactor physics standards. A wide variety of reactor physics methods and techniques are being used by reactor physicists for the design and analysis of modern reactors. ANSI (American National Standards Institute) reactor physics standards, covering such areas as nuclear data, reactor design, startup testing, decay heat and fast neutron fluence in the pressure vessel, are summarized and discussed. These standards are regularly undergoing review to respond to an evolving nuclear technology and are being successfully used in the U.S and abroad contributing to improvements in reactor design, safe operation and quality assurance. An overview of the overall program of reactor physics standards is presented. New standards currently under development are also discussed. (authors)

  12. MAPLE-X10 reactor safety assessment

    International Nuclear Information System (INIS)

    Cotnam, K.D.; Lounsbury, R.I.; Gillespie, G.E.

    1990-01-01

    This paper reports on the safety assessment of the 10 MW MAPLE-X10 reactor which has involved a substantial component of PSA analysis to supplement deterministic analysis. Initiating events are identified through the use of a master logic diagram. The events are then examined through event sequence diagrams, at the concept design stage, followed by a set of reliability analyses that are coordinated with the event sequence diagrams. Improvements identified through the reliability analyses are incorporated into the design to ensure that safety objectives are attained

  13. The concept of the sodium cooled small fast reactor 4S and the analyses of the loss of flow events

    International Nuclear Information System (INIS)

    Nishi, Yoshihisa; Ueda, Nobuyuki; Koga, Tomonari; Matsumiya, Hisato

    2007-01-01

    CRIEPI has been developing the 4S reactor (Super Safe, Small and Simple reactor) for application in dispersed energy supply and multipurpose use, in conjunction with Toshiba Corporation. The 4S is sodium cooled fast reactor and their electrical output has two options of 10MWe and 50MWe. In this paper, 10MWe 4S (4S-10M) was proposed. 4S-10M has some unique features. It employs a burn-up control system with annular reflector in place of the control rod that requires the frequent maintenance service. The core life time of the 4S-10M is 30 years and the fuel transport is not required during core life time. All temperature feedback coefficients are negative during core life time. In the latest design for 4S-10M, a pool and tall type reactor design was selected to reduce the construction cost. Two types of decay heat removal system (Reactor Vessel Auxiliary Cooling System; RVACS, Intermediate Reactor Auxiliary Cooling System; IRACS) using natural convection power were adopted. It is necessary to confirm that these two heat removal system can operate appropriately. The transition analyses were executed by the CERES code to evaluate the design feasibility and the thermal hydraulic characteristics of the 4S-10M. CERES is a multi-dimensional plant dynamics simulation code for liquid metal reactors developed by the CRIEPI. CERES can perform simulations ranging from forced circulation (full/partial power operation) to natural circulation. Components (pumps, IHXs, SGs, pipings, etc.) of the reactor are modeled as one-dimensional. Multi-dimensional plena are connected to such components. Two loss-of-flow accident sequences are considered. In the first case, it is assumed that the primary and the secondary pump were stopped by the total station black out. The reactor shut down system was assumed to be success. This sequence is referred to as the protected loss-of-flow accident (PLOF). In the second case, it is assumed that the reactor shut down systems fail to operate and the

  14. Multi-Robot Remote Interaction with FS-MAS

    Directory of Open Access Journals (Sweden)

    Yunliang Jiang

    2013-02-01

    Full Text Available The need to reduce bandwidth, improve productivity, autonomy and the scalability in multi-robot teleoperation has been recognized for a long time. In this article we propose a novel finite state machine mobile agent based on the network interaction service model, namely FS-MAS. This model consists of three finite state machines, namely the Finite State Mobile Agent (FS-Agent, which is the basic service module. The Service Content Finite State Machine (Content-FS, using the XML language to define workflow, to describe service content and service computation process. The Mobile Agent computation model Finite State Machine (MACM-FS, used to describe the service implementation. Finally, we apply this service model to the multi-robot system, the initial realization completing complex tasks in the form of multi-robot scheduling. This demonstrates that the robot has greatly improved intelligence, and provides a wide solution space for critical issues such as task division, rational and efficient use of resource and multi-robot collaboration.

  15. Utilization of RP-10 reactor for neutron therapy

    International Nuclear Information System (INIS)

    Paucar, R.; Nieto, M.; Parreno, F.; Vela, M.; Pozo, Z.

    1997-01-01

    In the Nuclear Energy Peruvian Institute, IPEN, a research area has established of Neutron Radiotherapy, know as NCT. This research joins the physics of particles (Neutrons and photons) and Medical Physics, and this one is an applied investigation where in considering the construction of a treatment hall in Huarangal (Peru) Reactor's irradiation facility, it can treat patients with brain tumors. In Neutron Therapy (NCT), it tries to use neutrons to destroy tumor cells where other therapeutic techniques are not effective. This process consist on to incise a neutrons beam of adequate characteristics over the tumor area of the patient. The neutrons used are of thermal energy and therefore irradiations are developed in experimental reactors. For this one, it is used horizontal channels prepared suitably. Before the irradiation, it is injected to the patient a substance which is absorbed by tumoral tissue. The substance components will be B-10, nuclide with an absorption cross section high to thermal neutrons (3837 b). The B-10 irradiate with thermal neutrons produce alpha particles of short reach (10 μm. on soft tissue) and with LET values (lineal energy transference) very high. The result is a cell preferential destruction which have absorbed the substance and it's next neighbors, like the cell size is 10 μm. This process as know as Boron Neutron Capture Therapy (BNCT). This work describes Peruvian RP-10 reactor and recently efforts to assess the design and feasibility of the medical neutron irradiation facility for NCT. (author). 22 refs., 6 tabs

  16. Water absorption and biodegradation kinetics of highly filled EOC-FS biocomposites

    Science.gov (United States)

    Zykova, A. K.; Pantyukhov, P. V.; Platov, Yu. T.; Bobojonova, G. A.; Ramos, C. Chaverri; Popov, A. A.

    2017-12-01

    The paper analyzes the water absorption and biodegradation kinetics in highly filled biocomposites based on ethylene-octene copolymer (EOC) and oil flax straw (FS). It is shown that adding the filler to EOC increases the water absorption from 0 to 22%. The tendency can be explained both by the low interfacial adhesion of EOC to FS and by the hydrophilic nature of the filler. According to biodegradation tests (10 months), the mass of pure EOC remains unchanged, suggesting that it fails to biodegrade in the environment. Increasing the filler content increases the weight loss of the composites and the degree of microbiological contamination (fungi filaments, bacteria) as evidenced by optical microscopy.

  17. Emission factors and congener-specific characterization of PCDD/Fs, PCBs, PBDD/Fs and PBDEs from an off-road diesel engine using waste cooking oil-based biodiesel blends.

    Science.gov (United States)

    Chen, Shui-Jen; Tsai, Jen-Hsiung; Chang-Chien, Guo-Ping; Huang, Kuo-Lin; Wang, Lin-Chi; Lin, Wen-Yinn; Lin, Chih-Chung; Yeh, C Kuei-Jyum

    2017-10-05

    Few studies have been performed up to now on the emission factors and congener profiles of persistent organic pollutants (POPs) emitted from off-road diesel engines. This investigation elucidates the emission factors and congener profiles of various POPs, namely polychlorinated dibenzo-p-dioxins and dibenzofurans (PCDD/Fs), polychlorinated biphenyl (PCBs), polybrominated dibenzo-p-dioxins and polybrominated dibenzofurans (PBDD/Fs) and polybrominated diphenyl ethers (PBDEs), in the exhausts of a diesel generator fueled with different waste cooking oil-based biodiesel (WCO-based biodiesel) blends. The PCDD/Fs contributed 87.2% of total dioxin-like toxicity (PCDD/Fs+PCBs+PBDD/Fs) in the exhaust, while the PCBs and PBDD/Fs only contributed 8.2% and 4.6%, respectively. Compared with petroleum diesel, B20 (20vol% WCO-based biodiesel+80vol% diesel) reduced total toxicity by 46.5% for PCDD/Fs, 47.1% for PCBs, and 24.5% for PBDD/Fs, while B40 (40vol% WCO-based biodiesel+60vol% diesel) reduced it by 89.5% for PCDD/Fs, 57.1% for PCBs, and 63.2% for PBDD/Fs in POP emission factors. The use of WCO-based biodiesel not only solves the problem of waste oil disposal, but also lowers POP emissions from diesel generators. Copyright © 2017 Elsevier B.V. All rights reserved.

  18. Active Noise Control Using Modified FsLMS and Hybrid PSOFF Algorithm

    Directory of Open Access Journals (Sweden)

    Ranjan Walia

    2018-04-01

    Full Text Available Active noise control is an efficient technique for noise cancellation of the system, which has been defined in this paper with the aid of Modified Filtered-s Least Mean Square (MFsLMS algorithm. The Hybrid Particle Swarm Optimization and Firefly (HPSOFF algorithm are used to identify the stability factor of the MFsLMS algorithm. The computational difficulty of the modified algorithm is reduced when compared with the original Filtered-s Least Mean Square (FsLMS algorithm. The noise sources are removed from the signal and it is compared with the existing FsLMS algorithm. The performance of the system is established with the normalized mean square error for two different types of noises. The proposed method has also been compared with the existing algorithms for the same purposes.

  19. Identification of Chemical Reactor Plant’s Mathematical Model

    OpenAIRE

    Pyakullya, Boris Ivanovich; Kladiev, Sergey Nikolaevich

    2015-01-01

    This work presents a solution of the identification problem of chemical reactor plant’s mathematical model. The main goal is to obtain a mathematical description of a chemical reactor plant from experimental data, which based on plant’s time response measurements. This data consists sequence of measurements for water jacket temperature and information about control input signal, which is used to govern plant’s behavior.

  20. Examination policy concerning the additional installation of No. 3 and No. 4 reactors in Takahama Nuclear Power Station and No. 3 and No. 4 reactors in Fukushima No. 2 Nuclear Power Station

    International Nuclear Information System (INIS)

    1980-01-01

    The Nuclear Safety Commission decided the annual examination policy on the modification of reactor installation in Takahama Nuclear Power Station to construct No. 3 and No. 4 reactors inquired under date of November 26, 1979, by the Minister of International Trade and Industry, so that the examination results of the accident in Three Mile Island nuclear power station are reflected to the examination for the purpose of improving reactor safety. The examination results of the accident in Three Mile Island power station are being investigated by the Committee on Examination of Reactor Safety, based on the policy shown in ''On the second report of the special committee examining the accident in a nuclear power station in the U.S.'' determined by the Nuclear Safety Commission under date of September 13, 1979. Though the Committee will further clarify the past guideline about the items concerning the criteria, design and operation management, the Committee decided the tentative policy to reflect it to safety examination. Further, a table is attached, in which 52 items to be reflected to the security measures are classified from the viewpoint of necessity to reflect them to the final examination. This table includes 13 items of criteria and examination, 7 items related to design, 10 items related to operation management, 10 antidisaster items, and 12 items related to safety research. (Wakatsuki, Y.)

  1. Radiation Protection Practices during the Helium Circulator Maintenance of the 10 MW High Temperature Gas-Cooled Reactor-Test Module (HTR-10

    Directory of Open Access Journals (Sweden)

    Chengxiang Guo

    2016-01-01

    Full Text Available Current radiation protection methodology offers abundant experiences on light-water reactors, but very few studies on high temperature gas-cooled reactor (HTR. To fill this gap, a comprehensive investigation was performed to the radiation protection practices in the helium circulator maintenance of the Chinese 10 MW HTR test module (HTR-10 in this paper. The investigation reveals the unique behaviour of HTR-10’s radiation sources in the maintenance as well as its radionuclide species and presents the radiation protection methods that were tailored to these features. Owing to these practices, the radioactivity level was kept low throughout the maintenance and only low-level radioactive waste was generated. The quantitative analysis further demonstrates that the decontamination efficiency was over 89% for surface contamination and over 34% for γ dose rate and the occupational exposure was much lower than both the limits of regulatory and the exposure levels in comparable literature. These results demonstrate the effectiveness of the reported radiation protection practices, which directly provides hands-on experience for the future HTR-PM reactor and adds to the completeness of the radiation protection methodology.

  2. Twenty years of Radiology in RP-10 nuclear reactor protection; Veinte anos de proteccion radiologica en el reactor nuclear RP-10

    Energy Technology Data Exchange (ETDEWEB)

    Zapata, Alejandro L.; Ramos, Fernando T.; Arrieta, Rolando W.B.; Vela Mora, Mariano, E-mail: lzapata@ipen.gob.pe, E-mail: framos@ipen.gob.pe, E-mail: rarrieta@ipen.gob.pe, E-mail: mvela@ipen.gob.pe [Instituto Peruano de Energia Nuclear (IPEN), Lima (Peru)

    2013-07-01

    In this report we present the results about radiation controls during 1990 - 2010, carried out in the Nuclear Reactor RP-10 of the Nuclear Center of Huarangal. These controls and radiological evaluation are of much utility for the radio personnel protection of this one and other reactors, since it allows to compares these variables with respect to the time. From the results obtained in monitoring and radiation controls, we conclude that in no case it has been reached the limits allowed by the Peruvian Regulating Authority. (author)

  3. TRIGA research reactors with higher power density

    International Nuclear Information System (INIS)

    Whittemore, W.L.

    1994-01-01

    The recent trend in new or upgraded research reactors is to higher power densities (hence higher neutron flux levels) but not necessarily to higher power levels. The TRIGA LEU fuel with burnable poison is available in small diameter fuel rods capable of high power per rod (≅48 kW/rod) with acceptable peak fuel temperatures. The performance of a 10-MW research reactor with a compact core of hexagonal TRIGA fuel clusters has been calculated in detail. With its light water coolant, beryllium and D 2 O reflector regions, this reactor can provide in-core experiments with thermal fluxes in excess of 3 x 10 14 n/cm 2 ·s and fast fluxes (>0.1 MeV) of 2 x 10 14 n/cm 2 ·s. The core centerline thermal neutron flux in the D 2 O reflector is about 2 x 10 14 n/cm 2 ·s and the average core power density is about 230 kW/liter. Using other TRIGA fuel developed for 25-MW test reactors but arranged in hexagonal arrays, power densities in excess of 300 kW/liter are readily available. A core with TRIGA fuel operating at 15-MW and generating such a power density is capable of producing thermal neutron fluxes in a D 2 O reflector of 3 x 10 14 n/cm 2 ·s. A beryllium-filled central region of the core can further enhance the core leakage and hence the neutron flux in the reflector. (author)

  4. Identification of Chemical Reactor Plant’s Mathematical Model

    Directory of Open Access Journals (Sweden)

    Pyakillya Boris

    2015-01-01

    Full Text Available This work presents a solution of the identification problem of chemical reactor plant’s mathematical model. The main goal is to obtain a mathematical description of a chemical reactor plant from experimental data, which based on plant’s time response measurements. This data consists sequence of measurements for water jacket temperature and information about control input signal, which is used to govern plant’s behavior.

  5. Design of SES-10 nuclear reactor for district heating

    International Nuclear Information System (INIS)

    Cuttler, J.M.

    1991-03-01

    The SES-10 units are unpressurized, pool-type nuclear reactors of 10MW rating, designed for supplying energy to hot water district heating systems, economically and without pollution. Water for heat distribution is brought to a maximum temperature of 85 degrees C. Conventional heating units supplement the output from SES-10 units for peak load and during maintenance. The SES-10 is housed in a low-cost building, with a double-walled pool in the ground. A naturally circulating primary system and a pumped secondary system transport heat from the reactor to the distribution system. The unit is fully automated and easy to maintain. Because of the many active and passive safety features, it is feasible to license the SES-10 for operation in a city and easy to explain it to the public for their acceptance. The core lasts approximately 43 months at a capacity factor of 70%, and the cost of heat is expected to be 2 to 2.5 cents/kWh

  6. Fact reactor fuel alloys: Retrospective and prospective views

    International Nuclear Information System (INIS)

    Nevitt, M.V.

    1989-01-01

    The relationship between the physical metallurgy of the EBR-II metallic fuel, U-5% Fs, and its performance in the reactor are described. An understanding of these relationships, along with the optimal matching of fuel properties to fuel-element design, have been essential in the 23 year successful utilization of the fuel. The knowledge and experience gained are being employed in the current development of a new U-Pu-Zr metallic fuel for a proposed advanced reactor (orig./MM)

  7. 256 fs, 2 nJ soliton pulse generation from MoS2 mode-locked fiber laser

    Science.gov (United States)

    Jiang, Zike; Chen, Hao; Li, Jiarong; Yin, Jinde; Wang, Jinzhang; Yan, Peiguang

    2017-12-01

    We demonstrate an Er-doped fiber laser (EDFL) mode-locked by a MoS2 saturable absorber (SA), delivering a 256 fs, 2 nJ soliton pulse at 1563.4 nm. The nonlinear property of the SA prepared by magnetron sputtering deposition (MSD) is measured with a modulation depth (MD) of ∼19.48% and a saturable intensity of 4.14 MW/cm2. To the best of our knowledge, the generated soliton pulse has the highest pulse energy of 2 nJ among the reported mode-locked EDFLs based on transition metal dichalcogenides (TMDs). Our results indicate that MSD-grown SAs could offer an exciting platform for high pulse energy and ultrashort pulse generation.

  8. 10 CFR 73.58 - Safety/security interface requirements for nuclear power reactors.

    Science.gov (United States)

    2010-01-01

    ... requirements for nuclear power reactors. (a) Each operating nuclear power reactor licensee with a license... 10 Energy 2 2010-01-01 2010-01-01 false Safety/security interface requirements for nuclear power reactors. 73.58 Section 73.58 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF...

  9. Generation of sub-100-fs Stokes pulses upon SRS in a barium nitrate crystal

    International Nuclear Information System (INIS)

    Konyashchenko, Aleksandr V; Losev, Leonid L; Tenyakov, S Yu

    2010-01-01

    72-fs pulses are generated at the first Stokes component frequency upon stimulated Raman scattering in a barium nitrate crystal for the radiation of the Ti 3+ :Al 2 O 3 laser with the pulse duration of 50 fs. The energy efficiency of conversion is 20%. The barium nitrate crystal was optically pumped by two consecutive orthogonally polarised chirped pulses with the following time compression of the Stokes radiation pulse. (nonlinear optical phenomena)

  10. Operating history of U.S. nuclear power reactors

    International Nuclear Information System (INIS)

    1974-01-01

    The operating history of U. S. nuclear power plants through December 31, 1974 has been collected. Included are those nuclear reactor facilities which produce electricity, even if in token amounts, or which are part of a development program concerned with the generation of electricity through the use of a nuclear reactor as a heat source. The information is based on data furnished by facility operators. The charts are plotted in terms of cumulative thermal energy as a function of time. Since only those shutdowns of five days or more are shown, the charts do not give a detailed history of plant operation. They do, however, give an overview of the operating history of a variety of developmental and experimental nuclear power reactors. The data show the yearly gross generation of electricity for each U. S. nuclear plant and, for civilian power plants, information on reactor availability and plant capacity factor. (U.S.)

  11. Research about reactor operator's personability characteristics and performance

    Energy Technology Data Exchange (ETDEWEB)

    Wei Li; He Xuhong; Zhao Bingquan [Tsinghua Univ., Institute of Nuclear Energy Technology, Beijing (China)

    2003-03-01

    To predict and evaluate the reactor operator's performance by personality characteristics is an important part of reactor operator safety assessment. Using related psychological theory combined with the Chinese operator's fact and considering the effect of environmental factors to personality analysis, paper does the research about the about the relationships between reactor operator's performance and personality characteristics, and offers the reference for operator's selection, using and performance in the future. (author)

  12. Safety-related parameters for the MAPLE research reactor and a comparison with the IAEA generic 10-MW research reactor

    International Nuclear Information System (INIS)

    Carlson, P.A.; Lee, A.G.; Smith, H.J.; Ellis, R.J.

    1989-07-01

    A summary is presented of some of the principle safety-related physics parameters for the MAPLE Research Reactor, and a comparison with the IAEA Generic 10-MW Reactor is given. This provides a means to assess the operating conditions and fuelling requirements for safe operation of the MAPLE Research Reactor under accepted standards

  13. Development of the IAEA’s Knowledge Preservation Portals for Fast Reactors and Gas-Cooled Reactors Knowledge Preservation

    International Nuclear Information System (INIS)

    Batra, C.; Menahem, D. Beraha; Kriventsev, V.; Monti, S.; Reitsma, F.; Grosbois, J. de; Khoroshev, M.; Gladyshev, M.

    2016-01-01

    Full text: The IAEA has been carrying out a dedicated initiative on fast reactor knowledge preservation since 2003. The main objectives of the Fast Reactor Knowledge Portal (FRKP) initiative are to, a) halt the on-going loss of information related to fast reactors (FR), and b) collect, retrieve, preserve and make accessible existing data and information on FR. This portal will help in knowledge sharing, development, search and discovery, collaboration and communication of fast reactor related information. On similar lines a Gas Cooled Fast Reactor Knowledge Preservation portal project also started in 2013. Knowledge portals are capable to control and manage both publicly available as well as controlled information. The portals will not only incorporate existing set of knowledge and information, but will also provide a systemic platform for further preservation of new developments. It will include fast reactor and gas cooled reactor document repositories, project workspaces for the IAEA’s Coordinated Research Projects (CRPs), Technical Meetings (TMs), forums for discussion, etc. The portal will also integrate a taxonomy based search tool, which will help using new semantic search capabilities for improved conceptual retrieve of documents. The taxonomy complies with international web standards as defined by the W3C (World Wide Web Consortium). (author

  14. Polybrominated dibenzo-p-dioxins and dibenzofurans (PBDD/Fs) in e-waste plastic in Nigeria.

    Science.gov (United States)

    Sindiku, O; Babayemi, J O; Tysklind, M; Osibanjo, O; Weber, R; Watson, A; Schlummer, M; Lundstedt, S

    2015-10-01

    Plastics from cathode ray tube (CRT) casings were sampled in Nigeria and analysed for their polybrominated dibenzo-p-dioxin and dibenzofuran (PBDD/F) content. PBDD/Fs, consisting mainly of PBDFs, were detected in BFR containing plastic with a median (mean) concentration of 18,000 ng/g (41,000 ng/g). The PBDD/Fs levels were highest in samples containing PBDEs, but the levels of PBDFs were two orders of magnitude higher than the levels reported in the technical PBDE mixtures and where frequently exceeding 1000 μg/g of PBDE content. These higher levels are likely to arise from additional transformation of PBDEs during production, use, recycling, or storage, but the processes responsible were not identified in this study. PBDD/Fs in CRT casings containing1,2-bistribromophenoxyethane (TBPE) were dominated by tetrabrominated dibenzo-p-dioxin (TBDDs) with concentrations around 10 μg/g of the TBPE content. The PBDD/Fs in CRT casings containing tetrabromobisphenol A (TBBPA) were found at concentrations around 0.1 μg/g of TBBPA levels. Casings treated with TBPE or TBBPA often contained PBDEs (and PBDF) as impurities-probably originating from recycled e-waste plastics. It was estimated that the 237,000 t of CRT casings stockpiled in Nigeria contain between 2 and 8 t of PBDD/Fs. The total PBDD/F contamination in polymers arising from total historic PBDE production/use is estimated in the order of 1000 t. TEQ values of CRT samples frequently exceeded the Basel Convention's provisional low POPs content of 15 ng TEQ/g. Due to the significant risks to health associated with PBDD/Fs, more detailed studies on the exposure routes from PBDD/Fs in stockpiles are needed.

  15. Decommissioning of a small reactor (BR3 reactor, Belgium)

    International Nuclear Information System (INIS)

    Dadoumont, J.; Massaut, V.; Klein, M.; Demeulemeester, Y.

    2002-01-01

    Since 1989, SCK-CEN has been dismantling its PWR reactor BR3 (Belgian Reactor No. 3). After gaining a great deal of experience in remote dismantling of highly radioactive components during the actual dismantling of the two sets of internals, the BR3 team completed the cutting of its reactor pressure vessel (RPV). During the feasibility phase of the RPV dismantling, a decision was made to cut it under water in the refuelling pool of the plant, after having removed it from its cavity. The RPV was cut into segments using a milling cutter and a bandsaw machine. These mechanical techniques have shown their ability for this kind of operations. Prior to the segmentation, the thermal insulation situated around the RPV was remotely removed and disposed of. The paper will describe all these operations. The BR3 decommissioning activities also include the dismantling of contaminated loops and equipment. After a careful sorting of the pieces, optimized management routes are selected in order to minimize the final amount of radioactive waste to be disposed of. Some development of different methods of decontamination were carried out: abrasive blasting (or sand blasting), chemical decontamination (Oxidizing-Reducing process using Cerium). The main goal of the decontamination program is to recycle most of the metallic materials either in the nuclear world or in the industrial world by reaching the respective recycling or clearance level. Overall the decommissioning of the BR3 reactor has shown the feasibility of performing such a project in a safe and economical way. Moreover, BR3 has developed methodologies and decontamination processes to economically reduce the amount of radwaste produced. (author)

  16. fs - kes ta on ja kust ta tuleb : [luuletused] / [Mesikepp, Indrek] fs

    Index Scriptorium Estoniae

    fs, pseud., 1971-

    2004-01-01

    Sisu: fs - kes ta on ja kust ta tuleb ; "töötasin arhiivis..." ; mustad puud mustas vees ; "on päev. on kylm. on öö..." ; "tead ju kyll..." ; "päiksest paistes päevad..." ; "mida sa teed kui on öö..."

  17. Low-Temperature Catalytic Decomposition of 130 Tetra- to Octa-PCDD/Fs Congeners over CuOX and MnOX Modified V2O5/TiO2-CNTs with the Assistance of O3.

    Science.gov (United States)

    Zhao, Rixiao; Jin, Dongdong; Yang, Hangsheng; Lu, Shengyong; Potter, Phillip M; Du, Cuicui; Peng, Yaqi; Li, Xiaodong; Yan, Jianhua

    2016-10-07

    In this study, a reliable and steady PCDD/F generation system was utilized to investigate the performance of catalysts, in which 130 congeners of tetra- to octapolychlorinated dibenzo-p-dioxins and dibenzofurans (PCDD/Fs) vapors were studied under simulated flue gas with/without O 3 . TiO 2 and carbon nanotubes (CNTs) supported vanadium oxides (VO X /TiO 2 -CNTs) modified with MnO X and CuO X , which were reported to be beneficial to the decomposition of model molecules, were found to have a negative effect on the removal of real PCDD/Fs in the simulated flue gas without O 3 . Moreover, the addition of MnO X presented different effects depending on whether CuO X existed in catalysts or not, which was also contrary to its effects on the degradation of model molecules. In an O 3 -containing atmosphere, low chlorination level PCDD/Fs congeners were removed well over VO X -MnO X /TiO 2 -CNTs, while high chlorination level PCDD/Fs congeners were removed well over VO X -CuO X /TiO 2 -CNTs. Fortunately, all PCDD/Fs congeners decomposed well over VO X -MnO X -CuO X /TiO 2 -CNTs. Finally, the effects of tetra- to octachlorination level for the adsorption and degradation behaviors of PCDD/Fs congeners were also investigated.

  18. 3S-R10 automated RBS system

    International Nuclear Information System (INIS)

    Norton, G.A.; Schroeder, J.B.; Klody, G.M.; Strathman, M.D.

    1989-01-01

    The NEC 3S-R10 automated RBS spectrometer system includes the features required for routine application of Rutherford backscattering (RBS) and related techniques for materials analysis in both research and industrial settings. The NEC Model 3SDH Pelletron accelerator system provides stable, monoenergetic beams of helium ions up to 3.3 MeV and protons to 2.2 MeV and has heavy ion capability. The analytical end station is the fully computerized Charles Evans and Associates Model RBS-400. Automated features include sample positioning (precision 4-axis goniometer), channeling alignment, polar plot generation, and data acquisition and reduction. Computer automation of accelerator and chamber functions includes storage and recall of operating parameters. Unattended data acquisition, e.g., overnight or over a weekend, is possible for up to 100 samples per batch for random orientation, rotating random or channeling analyses at any sample location. Single samples may be up to 50 cm in diameter. A laser for sample alignment and a TV for video monitoring are included. Simultaneous detection (up to 4 detectors) at normal and grazing angles, external control of grazing angle detector position, and transmission scattering capabiltiy enhance system flexibility. The system is also compatible with PIXE, NRA, and hydrogen forward-backscattering analyses. Data reduction is part of the computer system, which features displays (several formats) and manipulation of up to five spectra at one time using constant multipliers or point by point operations between spectra. (orig.)

  19. Evaluation of PCDD/Fs characterization in animal feed and feed additives.

    Science.gov (United States)

    Kim, MeeKyung; Kim, Sooyeon; Yun, Seon Jong; Kwon, Jin-Wook; Son, Seong-Wan

    2007-09-01

    Safety control of feed and feed additives is necessary to have safe food of animal origin. Based on media reports, nine incidents regarding dioxins and/or PCBs contaminations occurred worldwide during the last decade. Korea is a country which imports feed and feed additives. In this study, various kinds of feed and feed additives were analyzed to monitor the contamination level of dioxins. The level of PCDD/Fs in fish oil was the highest with a concentration of 23.33ngkg(-1), which is equivalent to a toxicological concentration of 4.68ngWHO-TEQ/kg. Feed from animals origin such as chicken meal, animal fat, fish meal, fish oil, and shell powder showed relatively higher concentrations of PCDD/Fs. Feed from plants origin, minerals, and additives ranged from non-detects for bit pulp and ethoxyquin to 8.28ngkg(-1) for dl-methionine. From a toxicological point of view, the highest concentration in vitamins was 0.08ngWHO-TEQ/kg among the feed additives. 2,3,4,7,8-PeCDF was the dominant congener in samples of fish oil, fish meal, and shell powder. Animal fat showed that the pattern of PCDD/Fs depends on the sources of contamination. A sample of animal fat showed 1,2,3,4,7,8-HxCDF and the other sample showed 1,2,3,4,7,8-HxCDD as a primary congener. Generally, low levels of PCDDs were detected in feed additives. Patterns of PCDD/Fs in choline chloride were different with that in choline chloride from an incident in Europe in 2000.

  20. Effective management of regulator RI/FS comments

    International Nuclear Information System (INIS)

    Wolinsky, S.M.; Lojek, D.; George, R.D.; Houser, S.M.; Strimbu, M.J.

    1995-01-01

    This paper describes a successful strategy that facilitates regulatory approval of CERCLA documents required by compliance agreement and CERCLA, based on the experience of Operable Unit 1, Waste Storage Area, of the Fernald Environmental Management Project (FEMP). This strategy, which has become the site standard at the FEMP, was instrumental in obtaining regulator approval of the OU1 RI and FS, and early approval of the Record of Decision during a very tight compliance agreement-driven schedule. This strategy can be applied at any DOE Superfund site, especially where there is need to recover lost schedule, an incentive to meet milestones early, a need to improve the relationship between the DOE and the regulators, or where the regulatory agencies have historically provided a large volume of comments on CERCLA documents. The strategy focuses on early identification and resolution of issues relating to draft RI/FS documents, as raised in regulatory agency review comments. This pro-active strategy has the potential for schedule and cost savings, as well as for improved communication between DOE and the regulators. The strategy includes preparation of a separate comment response document, integration of comment responses with RI/FS documents, development of a database of agency comments and their resolution, and sharing lessons learned with preparers of subsequent RI/FS documents. The paper provides background on the FEMP and describes the FEMP comment response strategy; DOE and regulator interface; the Sitewide Comment Database; networked electronic file management; the process for classifying, analyzing, and responding to comments; integration with base RI/FS documents; and a conclusion

  1. Effective management of regulator RI/FS comments

    Energy Technology Data Exchange (ETDEWEB)

    Wolinsky, S.M.; Lojek, D.; George, R.D.; Houser, S.M.; Strimbu, M.J.

    1995-12-31

    This paper describes a successful strategy that facilitates regulatory approval of CERCLA documents required by compliance agreement and CERCLA, based on the experience of Operable Unit 1, Waste Storage Area, of the Fernald Environmental Management Project (FEMP). This strategy, which has become the site standard at the FEMP, was instrumental in obtaining regulator approval of the OU1 RI and FS, and early approval of the Record of Decision during a very tight compliance agreement-driven schedule. This strategy can be applied at any DOE Superfund site, especially where there is need to recover lost schedule, an incentive to meet milestones early, a need to improve the relationship between the DOE and the regulators, or where the regulatory agencies have historically provided a large volume of comments on CERCLA documents. The strategy focuses on early identification and resolution of issues relating to draft RI/FS documents, as raised in regulatory agency review comments. This pro-active strategy has the potential for schedule and cost savings, as well as for improved communication between DOE and the regulators. The strategy includes preparation of a separate comment response document, integration of comment responses with RI/FS documents, development of a database of agency comments and their resolution, and sharing lessons learned with preparers of subsequent RI/FS documents. The paper provides background on the FEMP and describes the FEMP comment response strategy; DOE and regulator interface; the Sitewide Comment Database; networked electronic file management; the process for classifying, analyzing, and responding to comments; integration with base RI/FS documents; and a conclusion.

  2. The qualification of U3O8 as research reactor fuel

    International Nuclear Information System (INIS)

    Krull, W.

    1983-01-01

    This report summarizes the today knowledge of the qualification status of U 3 O 8 as low enriched ( 3 O 8 is so far qualified to start testing of ten (10) fuel elements with an U-density of 3.1 g U/cc in the FRG-2 research reactor. (orig.) [de

  3. Limits and conditions for continuous operation of WWR-S reactor

    International Nuclear Information System (INIS)

    Pittermann, P.; Listik, E.

    1979-02-01

    The fundamental technological and nuclear characteristics of the WWR-S reactor, safety limits and concepts of technical surveillance with particular attention to radiation safety of staff and of neighbouring population are outlined. The rules are mandatory for the reactor staff and for the users. The material is part of safety documentation for the WWR-S reactor. (author)

  4. Pressurized water reactors: the EPR project

    International Nuclear Information System (INIS)

    Py, J.P.; Yvon, M.

    2007-01-01

    EPR (originally 'European pressurized water reactor', and now 'evolutionary power reactor') is a model of reactor initially jointly developed by French and German engineers which fulfills the particular safety specifications of both countries but also the European utility requirements jointly elaborated by the main European power companies under the initiative of Electricite de France (EdF). Today, two EPR-based reactors are under development: one is under construction in Finland and the other, Flamanville 3 (France), received its creation permit decree on April 10, 2007. This article presents, first, the main objectives of the EPR, and then, describes the Flamanville 3 reactor: reactor type and general conditions, core and conditions of operation, primary and secondary circuits with their components, main auxiliary and recovery systems, man-machine interface and instrumentation and control system, confinement and serious accidents, arrangement of buildings. (J.S.)

  5. Design of SES-10 nuclear reactor for district heating

    International Nuclear Information System (INIS)

    Cuttler, J.M.

    1991-01-01

    The SES-10 units are unpressurized, pool-type nuclear reactors of 10 MW rating, designed for supplying energy to hot water district heating systems, economically and without pollution. Water for heat distribution is brought to a maximum temperature of 85 o C. Conventional heating units supplement the output from SES-10 units for peak load and during maintenance. The SES-10 is housed in a low-cost building, with a double-walled pool in the ground. A naturally circulating primary system and a pumped secondary system transport heat from the reactor to the distribution system. The unit is fully automated and easy to maintain. Because of the many active and passive safety features, it is feasible to license the SES-10 for operation in a city and easy to explain it to the public for their acceptance. The core lasts approximately 43 months at a capacity factor of 70%, and the cost of heat is expected to be 2 to 2.5 cents/kWh. (author) 8 figs

  6. Design of a 2 kA, 30 fs Rf-Photoinjector for Waterbag Compression

    Science.gov (United States)

    van der Geer, S. B.; Luiten, O. J.; de Loos, M. J.

    Because uniformly filled ellipsoidal ‘waterbag’ bunches have linear self-fields in all dimensions, they do not suffer from space-charge induced brightness degradation. This in turn allows very efficient longitudinal compression of high-brightness bunches at sub or mildly relativistic energies, a parameter regime inaccessible up to now due to detrimental effects of non-linear space-charge forces. To demonstrate the feasibility of this approach, we investigate ballistic bunching of 1 MeV, 100 pC waterbag electron bunches, created in a half-cell rf-photogun, by means of a two-cell booster-compressor. Detailed GPT simulations of this table-top set-up are presented, including realistic fields, 3D space-charge effects, path-length differences and image charges at the cathode. It is shown that with a single 10MW S-band klystron and fields of 100 MV/m, 2kA peak current is attainable with a pulse duration of only 30 fs at a transverse normalized emittance of 1.5 μm.

  7. Development of system analysis code for thermal-hydraulic simulation of integral reactor, Rex-10

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-10-15

    Rex-10 is an environment-friendly and economical small-scale nuclear reactor to provide the energy for district heating as well as the electric power in micro-grid. This integral reactor comprises several innovative concepts supported by advanced primary circuit components, low coolant parameters and natural circulation cooling. To evaluate the system performance and thermal-hydraulic behavior of the reactor, a system analysis code is being developed so that the new designs and technologies adopted in Rex-10 can be reflected. The research efforts are absorbed in programming the simple and fast-running thermal-hydraulic analysis software. The details of hydrodynamic governing equations component models and numerical solution scheme used in this code are presented in this paper. On the basis of one-dimensional momentum integral model, the models of point reactor neutron kinetics for thorium-fueled core, physical processes in the steam-gas pressurizer, and heat transfers in helically coiled steam generator are implemented to the system code. Implicit numerical scheme is employed to momentum and energy equations to assure the numerical stability. The accuracy of simulation is validated by applying the solution method to the Rex-10 test facility. Calculated natural circulation flow rate and coolant temperature at steady-state are compared to the experimental data. The validation is also carried out for the transients in which the sudden reduction in the core power or the feedwater flow takes place. The code's capability to predict the steady-state flow by natural convection and the qualitative behaviour of the primary system in the transients is confirmed. (Author)

  8. The feasibility study on commercialized fast reactor cycle system

    International Nuclear Information System (INIS)

    Noda, Hiroshi

    2002-01-01

    The feasibility study on commercialized Fast Reactor cycle system (FS) has been carried out by a joint team with the participation of all parties concerned in Japan since July, 1999. It aims to clarify various perspectives for commercialized fast reactor cycle system and also suggest development strategies to diverse social needs in the 21 st century. The FS consists of several phases. The phase 1 has progressed as planned and the highly feasible candidate concepts with innovative technologies have been screened out among a wide variety of concepts. During the phase 2, approximately five years after the phase 1, the in-depth design studies and engineering scale tests of key technologies are being conducted to verify and validate the feasibility of screened candidate concepts. At the end of the phase 2, a few promising concepts will be selected with their R and D tasks. The paper describes the results of the phase 1, the activities of the phase 2 and the new concept related to the fast reactor fuel cycle focusing on the reduction in environmental burden, which is one of key factors to sustain the nuclear power generation in the 21 st century

  9. Comparison of 2D and 3D Neutron Transport Analyses on Yonggwang Unit 3 Reactor

    International Nuclear Information System (INIS)

    Maeng, Aoung Jae; Kim, Byoung Chul; Lim, Mi Joung; Kim, Kyung Sik; Jeon, Young Kyou; Yoo, Choon Sung

    2012-01-01

    10 CFR Part 50 Appendix H requires periodical surveillance program in the reactor vessel (RV) belt line region of light water nuclear power plant to check vessel integrity resulting from the exposure to neutron irradiation and thermal environment. Exact exposure analysis of the neutron fluence based on right modeling and simulations is the most important in the evaluation. Traditional 2 dimensional (D) and 1D synthesis methodologies have been widely applied to evaluate the fast neutron (E > 1.0 MeV) fluence exposure to RV. However, 2D and 1D methodologies have not provided accurate fast neutron fluence evaluation at elevations far above or below the active core region. RAPTOR-M3G (RApid Parallel Transport Of Radiation - Multiple 3D Geometries) program for 3D geometries calculation was therefore developed both by Westinghouse Electronic Company, USA and Korea Reactor Integrity Surveillance Technology (KRIST) for the analysis of In-Vessel Surveillance Test and Ex-Vessel Neutron Dosimetry (EVND). Especially EVND which is installed at active core height between biological shielding material and concrete also evaluates axial neutron fluence by placing three dosimetries each at Top, Middle and Bottom part of the angle representing maximum neutron fluence. The EVND programs have been applied to the Korea Nuclear Plants. The objective of this study is therefore to compare the 3D and the 2D Neutron Transport Calculations and Analyses on the Yonggwang unit 3 Reactor as an example

  10. H3S10ph broadly marks early-replicating domains in interphase ESCs and shows reciprocal antagonism with H3K9me2.

    Science.gov (United States)

    Chen, Carol C L; Goyal, Preeti; Karimi, Mohammad M; Abildgaard, Marie H; Kimura, Hiroshi; Lorincz, Matthew C

    2018-01-01

    Phosphorylation of histone H3 at serine 10 (H3S10ph) by Aurora kinases plays an important role in mitosis; however, H3S10ph also marks regulatory regions of inducible genes in interphase mammalian cells, implicating mitosis-independent functions. Using the fluorescent ubiquitin-mediated cell cycle indicator (FUCCI), we found that 30% of the genome in interphase mouse embryonic stem cells (ESCs) is marked with H3S10ph. H3S10ph broadly demarcates gene-rich regions in G1 and is positively correlated with domains of early DNA replication timing (RT) but negatively correlated with H3K9me2 and lamin-associated domains (LADs). Consistent with mitosis-independent kinase activity, this pattern was preserved in ESCs treated with Hesperadin, a potent inhibitor of Aurora B/C kinases. Disruption of H3S10ph by expression of nonphosphorylatable H3.3S10A results in ectopic spreading of H3K9me2 into adjacent euchromatic regions, mimicking the phenotype observed in Drosophila JIL-1 kinase mutants . Conversely, interphase H3S10ph domains expand in Ehmt1 (also known as Glp ) null ESCs, revealing that H3S10ph deposition is restricted by H3K9me2. Strikingly, spreading of H3S10ph at RT transition regions (TTRs) is accompanied by aberrant transcription initiation of genes co-oriented with the replication fork in Ehmt1 -/- and Ehmt2 -/- ESCs, indicating that establishment of repressive chromatin on the leading strand following DNA synthesis may depend upon these lysine methyltransferases. H3S10ph is also anti-correlated with H3K9me2 in interphase murine embryonic fibroblasts (MEFs) and is restricted to intragenic regions of actively transcribing genes by EHMT2. Taken together, these observations reveal that H3S10ph may play a general role in restricting the spreading of repressive chromatin in interphase mammalian cells. © 2018 Chen et al.; Published by Cold Spring Harbor Laboratory Press.

  11. Mathematical Modelling of Catalytic Fixed-Bed Reactor for Carbon Dioxide Reforming of Methane over Rh/Al2O3 Catalyst

    Directory of Open Access Journals (Sweden)

    New Pei Yee

    2008-04-01

    Full Text Available A one-dimensional mathematical model was developed to simulate the performance of catalytic fixed bedreactor for carbon dioxide reforming of methane over Rh/Al2O3 catalyst at atmospheric pressure. The reactionsinvolved in the system are carbon dioxide reforming of methane (CORM and reverse water gas shiftreaction (RWGS. The profiles of CH4 and CO2 conversions, CO and H2 yields, molar flow rate and molefraction of all species as well as reactor temperature along the axial bed of catalyst were simulated. In addition,the effects of different reactor temperature on the reactor performance were also studied. The modelscan also be applied to analyze the performances of lab-scale micro reactor as well as pilot-plant scale reactorwith certain modifications and model verification with experimental data. © 2008 BCREC UNDIP. All rights reserved.[Received: 20 August 2008; Accepted: 25 September 2008][How to Cite: N.A.S. Amin, I. Istadi, N.P. Yee. (2008. Mathematical Modelling of Catalytic Fixed-Bed Reactor for Carbon Dioxide Reforming of Methane over Rh/Al2O3 Catalyst. Bulletin of Chemical Reaction Engineering and Catalysis, 3 (1-3: 21-29. doi:10.9767/bcrec.3.1-3.19.21-29

  12. History of fast reactor development in U.S.A.-I

    International Nuclear Information System (INIS)

    Ninokata, Hisashi; Sasao, Nobuyki

    2007-01-01

    History and present state of fast reactor was reviewed in series. As a history of fast reactor development in U.S.A. - I, this third lecture presented the dawn of the fast reactor development in the USA. The first fast reactor was the Clementine reactor with plutonium fuels and mercury coolant. The LAMPRE-1 reactor was the first sodium cooled and molten plutonium reactor. Experimental breeder reactor (EBR-1) was the first reactor to produce electricity and four kinds of fuels were loaded. Zero-power reactors were constructed to conduct reactor physics experiments on fast reactors. Today there are renewed interests in fast reactors due to their ability to fission actinides and reduce radioactive wastes. (T. Tanaka)

  13. ASN’s actions in GEN IV reactors and Sodium Fast Reactors (SFR)

    International Nuclear Information System (INIS)

    Belot, Clotilde

    2013-01-01

    The ASN is involved in 3 actions concerning GEN IV: • Overview of nuclear reactor GEN IV systems; • Specific analysis about transmutation; • Prototype reactor ASTRID (SFR). Furthermore theses actions are in the beginning (no conclusions or results available)

  14. EL3 reactor description and safety analysis report; Pile EL3, rapport descriptif et de surete

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1969-02-01

    The EL-3 reactor is an experimental pile. Heterogenous type reactor, water moderated and cooled it uses slightly enriched uranium oxide as fuel (4.5 percent) distributed in vertical cells that constitute the core (the maximum number of cells is 99). It is conceived to function at a maximal thermal power of 20 MW. It supplies a maximum thermal neutron flux of 10{sup 14} neutrons/cm{sup 2}/sec. It has several experimental devices. The EL-3 reactor is surrounded by auxiliary circuits of fluids, in a sealed containment, slightly depressed. The primary heavy water coolant circuit is completely included in this containment. Its cooling is made by the intermediary of a light water secondary circuit by atmospheric refrigerants. The ventilation circuits of the sealed containment and the reactor block do not release air outside, under nornal functioning, by a particularly studied chimney only after filtering and eventually dilution. The eventual contamination of the light water or air by active products is permanently monitored to allow the reactor shutdown and avoid the release in atmosphere of dangerous products. The EL-3 reactor, laying down in may 1955, has diverged in july 1957, made its first ascending in power in december 1957 and reached its complete power in april 1958. The positioning of actual fuel (snow crystal) was made during summer 1964. Reactor with an experimental aim, it is used for theoretical and technological studies by material irradiation in the experimental channels and the core cells, with possibilities to constitute independent loops (relative to the cooling fluids). Thirty vertical channels are devoted to the fabrication of artificial radioelements. [French] La pile EL-3 est une pile experimentale. Du type heterogene, moderee et refroidie a l'eau lourde elle utilise comme combustible de l'oxygene d'uranium faiblement enrichi (4,5 p.cent) reparti en cellules verticales qui constituent le coeur (le nombre maximal de cellules est de, 99). Elle est

  15. EL3 reactor description and safety analysis report; Pile EL3, rapport descriptif et de surete

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1969-02-01

    The EL-3 reactor is an experimental pile. Heterogenous type reactor, water moderated and cooled it uses slightly enriched uranium oxide as fuel (4.5 percent) distributed in vertical cells that constitute the core (the maximum number of cells is 99). It is conceived to function at a maximal thermal power of 20 MW. It supplies a maximum thermal neutron flux of 10{sup 14} neutrons/cm{sup 2}/sec. It has several experimental devices. The EL-3 reactor is surrounded by auxiliary circuits of fluids, in a sealed containment, slightly depressed. The primary heavy water coolant circuit is completely included in this containment. Its cooling is made by the intermediary of a light water secondary circuit by atmospheric refrigerants. The ventilation circuits of the sealed containment and the reactor block do not release air outside, under nornal functioning, by a particularly studied chimney only after filtering and eventually dilution. The eventual contamination of the light water or air by active products is permanently monitored to allow the reactor shutdown and avoid the release in atmosphere of dangerous products. The EL-3 reactor, laying down in may 1955, has diverged in july 1957, made its first ascending in power in december 1957 and reached its complete power in april 1958. The positioning of actual fuel (snow crystal) was made during summer 1964. Reactor with an experimental aim, it is used for theoretical and technological studies by material irradiation in the experimental channels and the core cells, with possibilities to constitute independent loops (relative to the cooling fluids). Thirty vertical channels are devoted to the fabrication of artificial radioelements. [French] La pile EL-3 est une pile experimentale. Du type heterogene, moderee et refroidie a l'eau lourde elle utilise comme combustible de l'oxygene d'uranium faiblement enrichi (4,5 p.cent) reparti en cellules verticales qui constituent le coeur (le nombre maximal de cellules est de, 99

  16. Technical report on implementation of reactor internal 3D modeling and visual database system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yeun Seung; Eom, Young Sam; Lee, Suk Hee; Ryu, Seung Hyun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-06-01

    In this report was described a prototype of reactor internal 3D modeling and VDB system for NSSS design quality improvement. For improving NSSS design quality several cases of the nuclear developed nation`s integrated computer aided engineering system, such as Mitsubishi`s NUWINGS (Japan), AECL`s CANDID (Canada) and Duke Power`s PASCE (USA) were studied. On the basis of these studies the strategy for NSSS design improvement system was extracted and detail work scope was implemented as follows : 3D modelling of the reactor internals were implemented by using the parametric solid modeler, a prototype system of design document computerization and database was suggested, and walk-through simulation integrated with 3D modeling and VDB was accomplished. Major effects of NSSS design quality improvement system by using 3D modeling and VDB are the plant design optimization by simulation, improving the reliability through the single design database system and engineering cost reduction by improving productivity and efficiency. For applying the VDB to full scope of NSSS system design, 3D modelings of reactor coolant system and nuclear fuel assembly and fuel rod were attached as appendix. 2 tabs., 31 figs., 7 refs. (Author) .new.

  17. Implementation of EAM and FS potentials in HOOMD-blue

    Science.gov (United States)

    Yang, Lin; Zhang, Feng; Travesset, Alex; Wang, Caizhuang; Ho, Kaiming

    HOOMD-blue is a general-purpose software to perform classical molecular dynamics simulations entirely on GPUs. We provide full support for EAM and FS type potentials in HOOMD-blue, and report accuracy and efficiency benchmarks, including comparisons with the LAMMPS GPU package. Two problems were selected to test the accuracy: the determination of the glass transition temperature of Cu64.5Zr35.5 alloy using an FS potential and the calculation of pair distribution functions of Ni3Al using an EAM potential. In both cases, the results using HOOMD-blue are indistinguishable from those obtained by the GPU package in LAMMPS within statistical uncertainties. As tests for time efficiency, we benchmark time-steps per second using LAMMPS GPU and HOOMD-blue on one NVIDIA Tesla GPU. Compared to our typical LAMMPS simulations on one CPU cluster node which has 16 CPUs, LAMMPS GPU can be 3-3.5 times faster, and HOOMD-blue can be 4-5.5 times faster. We acknowledge the support from Laboratory Directed Research and Development (LDRD) of Ames Laboratory.

  18. Monte Carlo Modeling Electronuclear Processes in Cascade Subcritical Reactor

    CERN Document Server

    Bznuni, S A; Zhamkochyan, V M; Polyanskii, A A; Sosnin, A N; Khudaverdian, A G

    2000-01-01

    Accelerator driven subcritical cascade reactor composed of the main thermal neutron reactor constructed analogous to the core of the VVER-1000 reactor and a booster-reactor, which is constructed similar to the core of the BN-350 fast breeder reactor, is taken as a model example. It is shown by means of Monte Carlo calculations that such system is a safe energy source (k_{eff}=0.94-0.98) and it is capable of transmuting produced radioactive wastes (neutron flux density in the thermal zone is PHI^{max} (r,z)=10^{14} n/(cm^{-2} s^{-1}), neutron flux in the fast zone is respectively equal PHI^{max} (r,z)=2.25 cdot 10^{15} n/(cm^{-2} s^{-1}) if the beam current of the proton accelerator is k_{eff}=0.98 and I=5.3 mA). Suggested configuration of the "cascade" reactor system essentially reduces the requirements on the proton accelerator current.

  19. The 10 MW multipurpose TRIGA reactor at Ongkharak Nuclear Research Center, Thailand

    International Nuclear Information System (INIS)

    Thurgood, B.E.; Razvi, J.; Whittemore, J.L.; Bhadrakom, K.

    1997-01-01

    General Atomics (GA), has been selected to lead a team of firms from the United States, Japan, Australia and Thailand to design, build and commission the Ongkharak Nuclear Research Center near Bangkok, Thailand, for the Office of Atomic Energy for Peace. The facilities to be provided comprise of: A Reactor Island, consisting of a 10 MW TRIGA reactor that takes full advantage of the inherent safety characteristics of uranium-zirconium hydride (UZrH) fuel; An Isotope Production Facility for the production of radioisotopes and radiopharmaceuticals using the TRIGA reactor; A Waste Processing and Storage Facility for the processing and storage of radioactive waste from the facility as well as other locations in Thailand. The centerpiece of the Center will be the TRIGA reactor, fueled with low-enriched UZrH fuel, cooled and moderated by light water, and reflected by beryllium and heavy water. The UZrH fueled reactor will have a rated steady state thermal power output of 10 MW, and will be capable of performing the following: Radioisotope production for medical, industrial and agricultural uses; Neutron transmutation doping of silicon; Beam experiments such as Neutron Scattering, Neutron Radiography (NR), and Prompt Gamma Neutron Activation Analysis (PGNAA); Medical therapy of patients using Boron Neutron Capture Therapy (BNCT); Applied research and technology development in the nuclear field; Training in principles of reactor operation, reactor physics, reactor experiments, etc. (author)

  20. Modification of an environmental surveillance program to monitor PCDD/Fs and metals around a municipal solid waste incinerator.

    Science.gov (United States)

    Vilavert, Lolita; Nadal, Martí; Mari, Montse; Schuhmacher, Marta; Domingo, José L

    2009-11-01

    Since the mid-90s, an environmental surveillance program has been on-going to provide information on the levels of PCDD/Fs and various metals in soil and vegetation samples collected in the vicinity of a municipal solid waste incinerator (MSWI) in Tarragona (Catalonia, Spain). However, the presence of other potential sources of pollution in the zone, such as traffic, forest fires, local industries, etc., makes hard to determine the impact concerning the MSWI. Therefore, in 2007 a change in the monitoring program was implemented by collecting additional ambient air samples through active and passive sampling devices. Mean PCDD/F levels in herbage and soil were 0.10 ng I-TEQ/kg dry weight (range: 0.05-0.17 ng I-TEQ/kg dw) and 0.64 ng I-TEQ/kg dw (range: 0.13-2.41 ng I-TEQ/kg dw), respectively. A significant reduction of the PCDD/F concentration in both monitors was observed with respect to our previous surveys. Air mean concentrations of PCDD/Fs were 12.04 and 15.21 fg WHO-TEQ/m(3) in 2007 and 2008, respectively, meaning a non-significant increase of 26%. In addition, a generalized increase of environmental metal levels with respect to our baseline study was not observed. The current concentrations of PCDD/Fs and metals in the vicinity of the MSWI of Tarragona are relatively low in comparison with other areas under the influence of emissions from waste incinerators. This indicates that the environmental impact of the MSWI of Tarragona is not significant. Moreover, the modification of the surveillance program has proven to be successful.

  1. Innovations and Enhancements for a Consortium of Big-10 University Research and Training Reactors. Final Report

    International Nuclear Information System (INIS)

    Brenizer, Jack

    2011-01-01

    The Consortium of Big-10 University Research and Training Reactors was by design a strategic partnership of seven leading institutions. We received the support of both our industry and DOE laboratory partners. Investments in reactor, laboratory and program infrastructure, allowed us to lead the national effort to expand and improve the education of engineers in nuclear science and engineering, to provide outreach and education to pre-college educators and students and to become a key resource of ideas and trained personnel for our U.S. industrial and DOE laboratory collaborators.

  2. Results of FY 2002 of feasibility study on commercialized fast reactor cycle systems. Phase 2

    International Nuclear Information System (INIS)

    2003-06-01

    Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Power Company (JAPC, that is the representative of the electric utilities in Japan) established a new organization to develop a commercialized fast reactor (FR) cycle system on July 1, 1999 and feasibility study (F/S) was undertaken in order to determine the promising concepts and to define the necessary R and D tasks. During Phase 1 (JFY 1999 and 2000), a number of candidate concepts were screened from various options, featuring innovative technologies. In the F/S, the options were evaluated and conceptual designs were examined considering the attainable perspectives for following: 1) ensuring safety, 2) economic competitiveness to future LWRs, 3) efficient utilization of resources, 4) reduction of environmental burden and 5) enhancement of nuclear non-proliferation. The F/S should also guide the necessary R and D to commercialize FR cycle system. To begin with the study of feasible candidate concepts screened in Phase I, Phase 2 started in the plan for five years in 2001. This aims at clarifying several feasible candidate concepts and deciding the research plan after Phase 3 as taking into consideration the innovative technology. As for this plan, an interim report will be carried out in 2003 as one pause and the prospect to clarify the feasible candidates will be expected. Furthermore, after the completion of this research and investigation program, research and development activities will be carried out under a rolling plan in which reviews will be carried out approximately every five years. The objective of these R and D activities is to make a proposal regarding highly attractive and competitive FR cycle system technology that assures safety by 2015. This report summarizes the results of F/S of Phase 2 in 2002. In 2002, the second year of Phase 2, the study was advanced along with the plan which was evaluated by the committee for the Evaluation. Then, in the study of FR system and fuel cycle

  3. Air quality assessment by tree bark biomonitoring in urban, industrial and rural environments of the Rhine Valley: PCDD/Fs, PCBs and trace metal evidence.

    Science.gov (United States)

    Guéguen, Florence; Stille, Peter; Millet, Maurice

    2011-09-01

    Tree barks were used as biomonitors to evaluate past atmospheric pollution within and around the industrial zones of Strasbourg (France) and Kehl (Germany) in the Rhine Valley. The here estimated residence time for trace metals, PCBs and PCDD/Fs in tree bark is >10 years. Thus, all pollution observed by tree bark biomonitoring can be older than 10 years. The PCB baseline concentration (sum of seven PCB indicators (Σ(7)PCB(ind))) determined on tree barks from a remote area in the Vosges mountains is 4 ng g(-1) and corresponds to 0.36 × 10(-3)ng toxic equivalent (TEQ) g(-1) for the dioxin-like PCBs (DL-PCBs). The northern Rhine harbor suffered especially from steel plant, waste incinerator and thermal power plant emissions. The polychlorinated dibenzo-p-dioxin and dibenzofuran (PCDD/Fs) concentrations analyzed in tree barks from this industrial area range between 392 and 1420 ng kg(-1) dry-weight (dw) corresponding to 3.9 ng TEQ(PCDD/Fs) kg(-1) to 17.8 ng TEQ(PCDD/Fs) kg(-1), respectively. Highest PCDD/F values of 7.2 ng TEQ kg(-1) to 17.8 ng TEQ kg(-1) have been observed close to and at a distance of fires might have been the reasons of these PCB enrichments. Other urban environments of the cities of Kehl and Strasbourg show significantly lower Σ(7)PCB(ind) concentrations. They suffer especially from road and river traffic and have typically Σ(7)PCB(ind) concentrations ranging from 11 ng g(-1) to 29 ng g(-1). The PCB concentration of 29 ng g(-1) has been found in tree bark close to the railway station of Strasbourg. Nevertheless, the corresponding TEQ(DL-PCB) are low and range between 0.2 × 10(-3) ng TEQ g(-1) and 7 × 10(-3) ng TEQ g(-1). Samples collected near road traffic are enriched in Fe, Sb, Sn and Pb. Cd enrichments were found close to almost all types of industries. Rural environments not far from industrial sites suffered from organic and inorganic pollution. In this case, TEQ(DL-PCB) values may reach up to 58 × 10(-3) ng TEQ g(-1) and the

  4. 76 FR 44964 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on U.S...

    Science.gov (United States)

    2011-07-27

    ... Subcommittee on U.S. Evolutionary Power Reactor; Notice of Meeting The ACRS Subcommittee on U.S. Evolutionary Power Reactor (U.S. EPR) will hold a meeting on August 18, 2011, Room T-2B3, 11545 Rockville Pike... the meeting, if possible, so that appropriate arrangements can be made. Thirty-five hard copies of...

  5. InterProScan Result: FS835133 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS835133 FS835133_5_ORF2 844B4637600527DB PIR PIRSF017267 Sulfiredoxin 8.2e-48 T IPR016692 Sulfire...doxin Molecular Function: sulfiredoxin activity (GO:0032542)|Biological Process: oxidation reduction (GO:0055114) ...

  6. Fundus oculi pigmentation studies simulating the fs-LASIK process Fundus oculi pigmentation studies simulating the fs-LASIK process

    Science.gov (United States)

    Sander, M.; Minet, O.; Zabarylo, U.; Müller, M.; Tetz, M. R.

    2012-06-01

    The femtosecond-laser in situ keratomileusis (fs-LASIK) technique has successfully entered the refractive surgery market to correct ametropia by cutting transparent corneal tissue with ultra-short laser pulses based on photodisruption. The laser pulses in the near infrared range (NIR) generate a laser-induced breakdown (LIOB) in the cornea. By propagating through the eye, a certain amount of the pulse is deposited in the cornea and the remaining energy interacts with the strong absorbing tissue behind. Due to the absorption by the retinal pigment epithelium and the transfer of the thermal energy to surrounding tissue, the transmitted energy can induce damage to the retina. The aim of this project was to find out the threshold influences concerning the tissue and the correlation between the results of the macroscopical appraisal and the fundus oculi pigmentation by simulating the fs-LASIK procedure with two various laser systems in the continuous wave (CW) and fs-regime. Therefore ex-vivo determinations were carried out macroscopically and histopathologically on porcine tissue.

  7. Broadband pump-probe spectroscopy with sub-10-fs resolution for probing ultrafast internal conversion and coherent phonons in carotenoids

    International Nuclear Information System (INIS)

    Polli, D.; Antognazza, M.R.; Brida, D.; Lanzani, G.; Cerullo, G.; De Silvestri, S.

    2008-01-01

    We use pump-probe spectroscopy with broadband detection to study electronic energy relaxation and coherent vibrational dynamics in carotenoids. A fast optical multichannel analyzer combined with a non-collinear optical parametric amplifier allows simultaneous acquisition of the differential transmission dynamics on the 500-700 nm wavelength range with sub-10-fs temporal resolution. The broad spectral coverage enables on the one hand a detailed study of the ultrafast bright-to-dark state internal conversion process; on the other hand, the tracking of the motion of the vibrational wavepacket launched on the ground state multidimensional potential energy surface. We present results on all-trans β-carotene and on a long-chain polyene in solution. The developed experimental setup enables the straightforward acquisition and analysis of coherent vibrational dynamics, highlighting time-frequency domain features with extreme resolution

  8. Measurement of the B{sub s}{sup 0}-B{sup Macron }{sub s}{sup 0} oscillation frequency {Delta}m{sub s} in B{sub s}{sup 0}{yields}D{sub s}{sup -}(3){pi} decays

    Energy Technology Data Exchange (ETDEWEB)

    Aaij, R. [Nikhef National Institute for Subatomic Physics, Amsterdam (Netherlands); Adeva, B. [Universidad de Santiago de Compostela, Santiago de Compostela (Spain); Adinolfi, M. [H.H. Wills Physics Laboratory, University of Bristol, Bristol (United Kingdom); Adrover, C. [CPPM, Aix-Marseille Universite, CNRS/IN2P3, Marseille (France); Affolder, A. [Oliver Lodge Laboratory, University of Liverpool, Liverpool (United Kingdom); Ajaltouni, Z. [Clermont Universite, Universite Blaise Pascal, CNRS/IN2P3, LPC, Clermont-Ferrand (France); Albrecht, J.; Alessio, F. [European Organization for Nuclear Research (CERN), Geneva (Switzerland); Alexander, M. [School of Physics and Astronomy, University of Glasgow, Glasgow (United Kingdom); Alkhazov, G. [Petersburg Nuclear Physics Institute (PNPI), Gatchina (Russian Federation); Alvarez Cartelle, P. [Universidad de Santiago de Compostela, Santiago de Compostela (Spain); Alves, A.A. [Sezione INFN di Roma La Sapienza, Roma (Italy); Amato, S. [Universidade Federal do Rio de Janeiro (UFRJ), Rio de Janeiro (Brazil); Amhis, Y. [Ecole Polytechnique Federale de Lausanne (EPFL), Lausanne (Switzerland); Anderson, J. [Physik-Institut, Universitaet Zuerich, Zuerich (Switzerland); Appleby, R.B. [School of Physics and Astronomy, University of Manchester, Manchester (United Kingdom); Aquines Gutierrez, O. [Max-Planck-Institut fuer Kernphysik (MPIK), Heidelberg (Germany); Archilli, F. [Laboratori Nazionali dell' INFN di Frascati, Frascati (Italy); European Organization for Nuclear Research (CERN), Geneva (Switzerland); Arrabito, L. [CC-IN2P3, CNRS/IN2P3, Lyon-Villeurbanne (France); Artamonov, A. [Institute for High Energy Physics (IHEP), Protvino (Russian Federation); and others

    2012-03-19

    The B{sub s}{sup 0}-B{sup Macron }{sub s}{sup 0} oscillation frequency {Delta}m{sub s} is measured with 36 pb{sup -1} of data collected in pp collisions at {radical}(s)=7 TeV by the LHCb experiment at the Large Hadron Collider. A total of 1381 B{sub s}{sup 0}{yields}D{sub s}{sup -}{pi}{sup +} and B{sub s}{sup 0}{yields}D{sub s}{sup -}{pi}{sup +}{pi}{sup -}{pi}{sup +} signal decays are reconstructed, with average decay time resolutions of 44 fs and 36 fs, respectively. An oscillation signal with a statistical significance of 4.6{sigma} is observed. The measured oscillation frequency is {Delta}m{sub s}=17.63{+-}0.11(stat){+-}0.02(syst) ps{sup -1}.

  9. InterProScan Result: FS891448 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS891448 FS891448_6_ORF1 45634B4CEFE7200E PROSITE PS00243 INTEGRIN_BETA NA T IPR015812 Integri...0)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  10. InterProScan Result: FS773973 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS773973 FS773973_5_ORF1 95C70FFD3346651F PROSITE PS00243 INTEGRIN_BETA NA T IPR015812 Integri...0)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  11. InterProScan Result: FS891448 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS891448 FS891448_6_ORF1 45634B4CEFE7200E PANTHER PTHR10082 INTEGRIN BETA SUBUNIT 8...-matrix adhesion (GO:0007160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  12. InterProScan Result: FS874648 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS874648 FS874648_2_ORF1 2CED241FB157BFCC PRINTS PR00309 ARRESTIN 7.8e-13 T IPR000698 Arrestin Biological... Process: signal transduction (GO:0007165)|Biological Process: sensory perception (GO:0007600) ...

  13. InterProScan Result: FS874648 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS874648 FS874648_2_ORF1 2CED241FB157BFCC PANTHER PTHR11792 ARRESTIN 1.9e-55 T IPR000698 Arrestin Biological... Process: signal transduction (GO:0007165)|Biological Process: sensory perception (GO:0007600) ...

  14. InterProScan Result: FS774270 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS774270 FS774270_5_ORF1 FB109746C115A036 PFAM PF04114 Gaa1 NA ? IPR007246 unintegrated Cellular... Component: integral to membrane (GO:0016021)|Cellular Component: GPI-anchor transamidase complex (GO:0042765) ...

  15. InterProScan Result: FS931761 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS931761 FS931761_2_ORF2 31D2C24B9731CAEC PFAM PF05753 TRAP_beta NA ? IPR008856 unintegrated Cellular... Component: endoplasmic reticulum (GO:0005783)|Cellular Component: integral to membrane (GO:0016021) ...

  16. InterProScan Result: FS880233 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS880233 FS880233_1_ORF2 88C10776BC024404 SUPERFAMILY SSF51621 Phosphoenolpyruvate/pyruva...te domain 1.9e-07 T IPR015813 Pyruvate/Phosphoenolpyruvate kinase, catalytic core Molecular Function: catalytic activity (GO:0003824) ...

  17. Integral test of JENDL-3.3 for fast reactors

    International Nuclear Information System (INIS)

    Chiba, Gou

    2003-01-01

    An integral test of JENDL-3.3 was performed for fast reactors. Various types of fast reactors were analyzed. Calculation values of the nuclear characteristics were greatly especially affected by the revisions of the cross sections of U-235 capture and elastic scattering reactions. The C/E values were improved for ZPPR cross where plutonium is mainly fueled, but not for BFS cores where uranium is mainly fueled. (author)

  18. A 20fs synchronization system for lasers and cavities in accelerators and FELs

    Science.gov (United States)

    Wilcox, R. B.; Byrd, J. M.; Doolittle, L. R.; Huang, G.; Staples, J. W.

    2010-02-01

    A fiber-optic RF distribution system has been developed for synchronizing lasers and RF plants in short pulse FELs. Typical requirements are 50-100fs rms over time periods from 1ms to several hours. Our system amplitude modulates a CW laser signal, senses fiber length using an interferometer, and feed-forward corrects the RF phase digitally at the receiver. We demonstrate less than 15fs rms error over 12 hours, between two independent channels with a fiber path length difference of 200m and transmitting S-band RF. The system is constructed using standard telecommunications components, and uses regular telecom fiber.

  19. The status of the PIK reactor

    Energy Technology Data Exchange (ETDEWEB)

    Petrov, Yu V [Academy of Sciences of Russia, Petersburg Nuclear Physics Institute, Gatchina, St. Petersburg (Russian Federation)

    1992-07-01

    This report describes the 100 MW research reactor PIK which is now under construction. The thermal neutron flux in the heavy water reflector exceeds 10{sup 15} cm{sup -2}s{sup -1}; in the light water trap, it is about 4{center_dot}10{sup 15} cm{sup -2}s{sup -1}. The replaceable core vessel allows to vary the parameters of the core over a wide range. The reactor provides sources of hot, cold and ultracold neutrons for 10 horizontal, 6 inclined neutron beams, and 8 neutron guides. At the ends of the beam tubes, the neutron flux is 10{sup 10} - 10{sup 11} cm{sup -2}s{sup -1}. The flux of the long wave neutrons exceeds 10{sup 9} cm{sup -2}s{sup -1}. To ensure precise measurements, the experimental hall is protected against vibrations. The project meets all modern safety requirements. The calculated parameters of the reactor were verified using a full-scale mock-up. Seventy percent of the reactor construction and installation were completed in the beginning of 1992. (author)

  20. InterProScan Result: FS755117 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS755117 FS755117_5_ORF1 848EA0528A797D85 PANTHER PTHR21347 CLEFT LIP AND PALATE ASSOCIATED TRANSME...MBRANE PROTEIN-RELATED 2.9e-76 T IPR008429 Cleft lip and palate transmembrane 1 ...

  1. InterProScan Result: FS742531 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS742531 FS742531_5_ORF1 83DE48A0149BB5E1 PANTHER PTHR23154 LEUCINE-RICH TRANSMEMBR...ANE PROTEINS 1.7e-16 T IPR000157 unintegrated Molecular Function: transmembrane receptor activity (GO:000488

  2. InterProScan Result: FS932793 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS932793 FS932793_2_ORF2 6EA452AE762D110F PANTHER PTHR12479:SF4 LYSOSOMAL-ASSOCIATED TRANSME...MBRANE PROTEIN 4.4e-71 T IPR018400 Lysosomal-associated transmembrane protein, CG14767-PB ...

  3. InterProScan Result: FS756793 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS756793 FS756793_1_ORF2 CD4194218B70284D PRINTS PR01186 INTEGRINB 5.5e-17 T IPR015812 Integri...0)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  4. InterProScan Result: FS773973 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS773973 FS773973_5_ORF1 95C70FFD3346651F PRINTS PR01186 INTEGRINB 1.6e-17 T IPR015812 Integri...0)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  5. InterProScan Result: FS885315 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS885315 FS885315_1_ORF2 BB16E7B6C4656671 PANTHER PTHR10082 INTEGRIN BETA SUBUNIT 6...-matrix adhesion (GO:0007160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  6. InterProScan Result: FS911973 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS911973 FS911973_1_ORF2 2E2F43F4558B5288 PANTHER PTHR11792 ARRESTIN 2.6e-53 T IPR000698 Arrestin Biological... Process: signal transduction (GO:0007165)|Biological Process: sensory perception (GO:0007600) ...

  7. InterProScan Result: FS911973 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS911973 FS911973_1_ORF2 2E2F43F4558B5288 PRINTS PR00309 ARRESTIN 4.7e-22 T IPR000698 Arrestin Biological... Process: signal transduction (GO:0007165)|Biological Process: sensory perception (GO:0007600) ...

  8. InterProScan Result: FS726027 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS726027 FS726027_2_ORF2 C7058CD552BC398B PFAM PF01545 Cation_efflux NA ? IPR002524 unintegrated Biological...nsporter activity (GO:0008324)|Cellular Component: membrane (GO:0016020)|Biological Process: transmembrane transport (GO:0055085) ...

  9. InterProScan Result: FS919781 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS919781 FS919781_2_ORF2 11D6928E8BA64F8F SUPERFAMILY SSF55194 Ribosome recycling f...actor, RRF 5.5e-35 T IPR002661 Ribosome recycling factor Biological Process: translation (GO:0006412) ...

  10. InterProScan Result: FS895314 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS895314 FS895314_5_ORF1 97DB8176F1361E8C SUPERFAMILY SSF51621 Phosphoenolpyruvate/pyruva...te domain 1e-21 T IPR015813 Pyruvate/Phosphoenolpyruvate kinase, catalytic core Molecular Function: catalytic activity (GO:0003824) ...

  11. Sensitivity analysis of reflector types and impurities in 10 MW MTR type nuclear research reactor

    International Nuclear Information System (INIS)

    Khattab, K.; Khamis, I.

    2007-01-01

    The 2-D and 3-D neutronics models for 10 MW nuclear research reactor of MTR type have been developed and presented in this paper. Our results agree very well with the results of seven countries mentioned in the IAEA-TECDOC-233. To study the effect of reflector types on the reactor effective multiplication factor, five types of reflectors such as pure beryllium, beryllium, heavy water, carbon and water are selected for this study. The pure beryllium is found to be the most efficient reflector in this group. The effect of the most important impurities, which exist on the beryllium reflector such as iron, silicon and aluminium on the reactor multiplication factor, have been analyzed as well. It is found that the iron impurity affects the reactor multiplication factor the most compared to silicon and aluminium impurities. (author)

  12. Radiation resistant fiber Bragg grating in random air-line fibers for sensing applications in nuclear reactor cores.

    Science.gov (United States)

    Zaghloul, Mohamed A S; Wang, Mohan; Huang, Sheng; Hnatovsky, Cyril; Grobnic, Dan; Mihailov, Stephen; Li, Ming-Jun; Carpenter, David; Hu, Lin-Wen; Daw, Joshua; Laffont, Guillaume; Nehr, Simon; Chen, Kevin P

    2018-04-30

    This paper reports the testing results of radiation resistant fiber Bragg grating (FBG) in random air-line (RAL) fibers in comparison with FBGs in other radiation-hardened fibers. FBGs in RAL fibers were fabricated by 80 fs ultrafast laser pulse using a phase mask approach. The fiber Bragg gratings tests were carried out in the core region of a 6 MW MIT research reactor (MITR) at a steady temperature above 600°C and an average fast neutron (>1 MeV) flux >1.2 × 10 14 n/cm 2 /s. Fifty five-day tests of FBG sensors showed less than 5 dB reduction in FBG peak strength after over 1 × 10 20 n/cm 2 of accumulated fast neutron dose. The radiation-induced compaction of FBG sensors produced less than 5.5 nm FBG wavelength shift toward shorter wavelength. To test temporal responses of FBG sensors, a number of reactor anomaly events were artificially created to abruptly change reactor power, temperature, and neutron flux over short periods of time. The thermal sensitivity and temporal responses of FBGs were determined at different accumulated doses of neutron flux. Results presented in this paper reveal that temperature-stable Type-II FBGs fabricated in radiation-hardened fibers can survive harsh in-pile conditions. Despite large parameter drift induced by strong nuclear radiation, further engineering and innovation on both optical fibers and fiber devices could lead to useful fiber sensors for various in-pile measurements to improve safety and efficiency of existing and next generation nuclear reactors.

  13. Fusion blankets for catalyzed D--D and D--He3 reactors

    International Nuclear Information System (INIS)

    Fillo, J.A.; Powell, J.R.

    1977-01-01

    Blanket designs are presented for catalyzed D-D (Cat-D) and D-He 3 fusion reactors. Because of relatively low neutron wall loads and the flexibility due to non-tritium breeding, blankets potentially should operate for reactor life-times of approximately 30 years. Unscheduled replacement of failed blanket modules should be relatively rapid, due to very low residual activity, by operators working either through access ports in the shield (option 1) or directly in the plasma chamber (option 2). Cat-D blanket designs are presented for high (approximately 30%) and low (approximately 12%) β noncircular Tokamak reactors. The blankets are thick graphite screens, operating at high temperature to anneal radiation damage; the deposited neutron and gamma energy is thermally radiated along internal cavities and conducted to a bank of internal SiC coolant tubes (approximately 4 cm. ID) containing high pressure helium. In the D-He 3 Tokamak reactor design, the blanket consists of multiple layers (e.g., three) of thin (approximately 10 cm.) high strength aluminum (e.g., SAP), modular plates, cooled by organic terphynyl coolant

  14. Fusion blankets for catalyzed D--D and D--3He reactors

    International Nuclear Information System (INIS)

    Fillo, J.A.; Powell, J.R.

    1977-01-01

    Blanket designs are presented for catalyzed D-D (Cat-D) and D-He 3 fusion reactors. Because of relatively low neutron wall loads and the flexibility due to non-tritium breeding, blankets potentially should operate for reactor life-times of approximately 30 years. Unscheduled replacement of failed blanket modules should be relatively rapid, due to very low residual activity, by operators working either through access ports in the shield (option 1) or directly in the plasma chamber (option 2). Cat-D blanket designs are presented for high (approximately 30%) and low (approximately 12%) β non-circular Tokamak reactors. The blankets are thick graphite screens, operating at high temperature to anneal radiation damage; the deposited neutron and gamma energy is thermally radiated along internal cavities and conducted to a bank of internal SiC coolant tubes (approximately 4 cm. ID) containing high pressure helium. In the D-He 3 Tokamak reactor design, the blanket consists of multiple layers (e.g., three) of thin (approximately 10 cm.) high strength aluminum (e.g., SAP), modular plates, cooled by organic terphenyl coolant

  15. A Shielding Analysis of Hot Cell for a 10 MW Research Reactor

    International Nuclear Information System (INIS)

    Alnajjar, Alaaddin; Park, Chang Je; Roh, Gyuhong; Lee, Byunchul

    2013-01-01

    In this paper, a shielding analysis has been performed for the hot cell in a 10 MW research reactor. Two kinds of shielding analysis code systems are used such as MCNPX2.7 and M-Shield7. The first one is Monte Carlo stochastic code and the second one is a deterministic point kernel code. The results are compared in this study. In order to obtain source term, the ORIGEN-S code is used for different kinds of source. Four kinds of sources are taken into consideration. From the simulation, it is also proposed that the proper thickness of shielding material and the maximum source capacity in the hot cell. This study shows preliminary analysis results of hot cell shielding for 10MW research reactor. Total four different source terms are considered such as spent fuel assembly, Ir-192, Mo-99, and I-131. For shielding material, general concrete, heavy concrete, and lead are used. MCNPX code is mainly used for a simplified hot cell model and the result are nearly consistent when compared with M-Shield code. Required shielding thickness and the hot cell capacity are also obtained for various criterion of surface dose rates

  16. Burnup measurements on spent fuel elements of the RP-10 research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Vela Mora, Mariano; Gallardo Padilla, Alberto; Palomino, Jose Luis Castro, E-mail: mvela@ipen.gob.p [Instituto Peruano de Energia Nuclear (IPEN/Peru), Lima (Peru). Grupo de Calculo, Analisis y Seguridad de Reactores; Terremoto, Luis Antonio Albiac, E-mail: laaterre@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    This work describes the measurement, using nondestructive gamma-ray spectroscopy, of the average burnup attained by Material Testing Reactor (MTR) fuel elements irradiated in the RP-10 research reactor. Measurements were performed at the reactor storage pool area using {sup 137}Cs as the only burnup monitor, even for spent fuel elements with cooling times much shorter than two years. The experimental apparatus was previously calibrated in efficiency to obtain absolute average burnup values, which were compared against corresponding ones furnished by reactor physics calculations. The mean deviation between both values amounts to 6%. (author)

  17. Burnup measurements on spent fuel elements of the RP-10 research reactor

    International Nuclear Information System (INIS)

    Vela Mora, Mariano; Gallardo Padilla, Alberto; Palomino, Jose Luis Castro

    2011-01-01

    This work describes the measurement, using nondestructive gamma-ray spectroscopy, of the average burnup attained by Material Testing Reactor (MTR) fuel elements irradiated in the RP-10 research reactor. Measurements were performed at the reactor storage pool area using 137 Cs as the only burnup monitor, even for spent fuel elements with cooling times much shorter than two years. The experimental apparatus was previously calibrated in efficiency to obtain absolute average burnup values, which were compared against corresponding ones furnished by reactor physics calculations. The mean deviation between both values amounts to 6%. (author)

  18. InterProScan Result: FS766396 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS766396 FS766396_2_ORF2 2EA98AF8E0AD3165 PANTHER PTHR21347 CLEFT LIP AND PALATE ASSOCIATED TRANSME...MBRANE PROTEIN-RELATED 6.4e-05 T IPR008429 Cleft lip and palate transmembrane 1 ...

  19. InterProScan Result: FS859736 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS859736 FS859736_6_ORF2 45B8287CF5DB2D42 PANTHER PTHR21347 CLEFT LIP AND PALATE ASSOCIATED TRANSME...MBRANE PROTEIN-RELATED 1.1e-92 T IPR008429 Cleft lip and palate transmembrane 1 ...

  20. InterProScan Result: FS875135 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS875135 FS875135_2_ORF1 D56AE7CE71BA567E PANTHER PTHR10082 INTEGRIN BETA SUBUNIT 8...-matrix adhesion (GO:0007160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  1. InterProScan Result: FS875135 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS875135 FS875135_2_ORF1 D56AE7CE71BA567E PROSITE PS00243 INTEGRIN_BETA NA T IPR015812 Integri...0)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  2. InterProScan Result: FS888414 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS888414 FS888414_1_ORF2 7BD3608BC4DF6C01 PANTHER PTHR10082 INTEGRIN BETA SUBUNIT 2...-matrix adhesion (GO:0007160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  3. InterProScan Result: FS860732 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS860732 FS860732_6_ORF1 0375CFA2D74CE0C2 PROSITE PS00243 INTEGRIN_BETA NA T IPR015812 Integri...0)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  4. InterProScan Result: FS787904 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS787904 FS787904_5_ORF1 F46B8A7F4DCFA20B SUPERFAMILY SSF55194 Ribosome recycling f...actor, RRF 4.1e-24 T IPR002661 Ribosome recycling factor Biological Process: translation (GO:0006412) ...

  5. InterProScan Result: FS869255 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS869255 FS869255_4_ORF1 7290E0DA14F8EDE2 SUPERFAMILY SSF51621 Phosphoenolpyruvate/pyruva...te domain 1.1e-55 T IPR015813 Pyruvate/Phosphoenolpyruvate kinase, catalytic core Molecular Function: catalytic activity (GO:0003824) ...

  6. The U.S. Geological Survey's TRIGA® reactor

    Science.gov (United States)

    DeBey, Timothy M.; Roy, Brycen R.; Brady, Sally R.

    2012-01-01

    The U.S. Geological Survey (USGS) operates a low-enriched uranium-fueled, pool-type reactor located at the Federal Center in Denver, Colorado. The mission of the Geological Survey TRIGA® Reactor (GSTR) is to support USGS science by providing information on geologic, plant, and animal specimens to advance methods and techniques unique to nuclear reactors. The reactor facility is supported by programs across the USGS and is organizationally under the Associate Director for Energy and Minerals, and Environmental Health. The GSTR is the only facility in the United States capable of performing automated delayed neutron analyses for detecting fissile and fissionable isotopes. Samples from around the world are submitted to the USGS for analysis using the reactor facility. Qualitative and quantitative elemental analyses, spatial elemental analyses, and geochronology are performed. Few research reactor facilities in the United States are equipped to handle the large number of samples processed at the GSTR. Historically, more than 450,000 sample irradiations have been performed at the USGS facility. Providing impartial scientific information to resource managers, planners, and other interested parties throughout the world is an integral part of the research effort of the USGS.

  7. Nonsequential double ionization of D2 molecules with intense 20-fs pulses

    DEFF Research Database (Denmark)

    Sakai, H.; Larsen, J.J.; Wendt-Larsen, I.

    2003-01-01

    The kinetic-energy distribution of D+ fragments obtained from the ionization of D2 molecules with intense 20-fs pulses includes a high-energy component extending up to ˜10 eV. These fragments are only present for linearly, or slightly elliptically, polarized light. Both the maximum kinetic...

  8. Expression of chemokine CXCL12 and its receptor CXCR4 in folliculostellate (FS) cells of the rat anterior pituitary gland: the CXCL12/CXCR4 axis induces interconnection of FS cells.

    Science.gov (United States)

    Horiguchi, Kotaro; Ilmiawati, Cimi; Fujiwara, Ken; Tsukada, Takehiro; Kikuchi, Motoshi; Yashiro, Takashi

    2012-04-01

    The anterior pituitary gland is composed of five types of hormone-producing cells plus folliculostellate (FS) cells, which do not produce classical anterior pituitary hormones. FS cells are interconnected by cytoplasmic processes and encircle hormone-producing cells or aggregate homophilically. Using living-cell imaging of primary culture, we recently reported that some FS cells precisely extend their cytoplasmic processes toward other FS cells and form interconnections with them. These phenomena suggest the presence of a chemoattractant factor that facilitates the interconnection. In this study, we attempted to discover the factor that induces interconnection of FS cells and succeeded in identifying chemokine (CXC)-L12 and its receptor CXCR4 as potential candidate molecules. CXCL12 is a chemokine of the CXC subfamily. It exerts its effects via CXCR4, a G protein-coupled receptor. The CXCL12/CXCR4 axis is a potent chemoattractant for many types of neural cells. First, we revealed that CXCL12 and CXCR4 are expressed by FS cells in rat anterior pituitary gland. Next, to clarify the function of the CXCL12/CXCR4 axis in FS cells, we observed living anterior pituitary cells in primary culture with specific CXCL12 inhibitor or CXCR4 antagonist and noted that extension of cytoplasmic processes and interconnection of FS cells were inhibited. Finally, we examined FS cell migration and invasion by using Matrigel matrix assays. CXCL12 treatment resulted in markedly increased FS cell migration and invasion. These data suggest that FS cells express chemokine CXCL12 and its receptor CXCR4 and that the CXCL12/CXCR4 axis evokes interconnection of FS cells.

  9. InterProScan Result: FS756793 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS756793 FS756793_1_ORF2 CD4194218B70284D PANTHER PTHR10082 INTEGRIN BETA SUBUNIT 4e-37 T IPR001169 Integri...atrix adhesion (GO:0007160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  10. InterProScan Result: FS773973 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS773973 FS773973_5_ORF1 95C70FFD3346651F PANTHER PTHR10082 INTEGRIN BETA SUBUNIT 9e-32 T IPR001169 Integri...atrix adhesion (GO:0007160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  11. InterProScan Result: FS783191 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS783191 FS783191_5_ORF1 072DBEF328F41109 PFAM PF04192 Utp21 5e-59 T IPR007319 Small-subunit process...ome, Utp21 Biological Process: rRNA processing (GO:0006364)|Cellular Component: small-subunit processome (GO:0032040) ...

  12. InterProScan Result: FS873128 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS873128 FS873128_4_ORF1 97398CBF49C72044 PFAM PF08625 Utp13 2.9e-34 T IPR013934 Small-subunit process...ome, Utp13 Biological Process: rRNA processing (GO:0006364)|Cellular Component: small-subunit processome (GO:0032040) ...

  13. Distributing CMS Data between the Florida T2 and T3 Centers using Lustre and Xrootd-fs

    International Nuclear Information System (INIS)

    Kaganas, G; Rodriguez, J L; Cheng, M; Avery, P; Bourilkov, D; Fu, Y; Palencia, J

    2014-01-01

    We have developed remote data access for large volumes of data over the Wide Area Network based on the Lustre filesystem and Kerberos authentication for security. In this paper we explore a prototype for two-step data access from worker nodes at Florida Tier3 centers, located behind a firewall and using a private network, to data hosted on the Lustre filesystem at the University of Florida CMS Tier2 center. At the Tier3 center we use a client which mounts securely the Lustre filesystem and hosts an XrootD server. The worker nodes access the data from the Tier3 client using POSIX compliant tools via the XrootD-fs filesystem. We perform scalability tests with up to 200 jobs running in parallel on the Tier3 worker nodes.

  14. Nuclear research reactor 0.5 to 3 MW

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-05-15

    This nuclear reactor has been designed for radioisotope production, basic and applied research in reactor physics and nuclear engineering, neutron-beam experimentation, irradiation of various materials and training of scientific and technical personnel. It is located in the 'Production Area' of the Nuclear Technology Center. It is equipped with the necessary facilities for large-scale production of radioisotopes to be used in medicine as well as for other scientific and industrial purposes. In addition, it has a Neutronography Facility and the required equipment to perform Neutron-Activation Analysis. It is an open pool-type reactor, moderated and cooled with light water, fuelled with 20% enriched uranium. Its reflector are graphite and water. It has plate-type fuel elements clad in aluminium. The reactor core is located near the bottom of the demineralized water pool. It includes fuel elements, reflector and sample-holding devices for materials to be irradiated. This kind of configuration, which is widely used in research reactors, provides a high degree of safety since it prevents the core from becoming exposed under any circumstance and does not require any cooling system during reactor shutdown. Power output is between 0.5 to 3 MW{sub TH}, with a minimum thermal neutron flux of approx, 10{sup 13} n/cm{sup 2}{center_dot}sec, at irradiation zone almost with no modifications. Heat extraction is achieved by means of a cooling circuit which comprises two circulation pumps and a plate-type heat exchanger. Final heat dissipation to the atmosphere is performed through another cooling circuit which includes two circulation pumps and a cooling tower. Reactor control is accomplished with five neutron-absorbing rods positioned by means of especially designed elements and governed by the reactor's instrumentation and control system. Should an abnormal situation arise, gravity causes the rods to fall automatically, thus extinguishing the nuclear reaction. The reactor

  15. Nuclear research reactor 0.5 to 3 MW

    International Nuclear Information System (INIS)

    1992-05-01

    This nuclear reactor has been designed for radioisotope production, basic and applied research in reactor physics and nuclear engineering, neutron-beam experimentation, irradiation of various materials and training of scientific and technical personnel. It is located in the 'Production Area' of the Nuclear Technology Center. It is equipped with the necessary facilities for large-scale production of radioisotopes to be used in medicine as well as for other scientific and industrial purposes. In addition, it has a Neutronography Facility and the required equipment to perform Neutron-Activation Analysis. It is an open pool-type reactor, moderated and cooled with light water, fuelled with 20% enriched uranium. Its reflector are graphite and water. It has plate-type fuel elements clad in aluminium. The reactor core is located near the bottom of the demineralized water pool. It includes fuel elements, reflector and sample-holding devices for materials to be irradiated. This kind of configuration, which is widely used in research reactors, provides a high degree of safety since it prevents the core from becoming exposed under any circumstance and does not require any cooling system during reactor shutdown. Power output is between 0.5 to 3 MW TH , with a minimum thermal neutron flux of approx, 10 13 n/cm 2 ·sec, at irradiation zone almost with no modifications. Heat extraction is achieved by means of a cooling circuit which comprises two circulation pumps and a plate-type heat exchanger. Final heat dissipation to the atmosphere is performed through another cooling circuit which includes two circulation pumps and a cooling tower. Reactor control is accomplished with five neutron-absorbing rods positioned by means of especially designed elements and governed by the reactor's instrumentation and control system. Should an abnormal situation arise, gravity causes the rods to fall automatically, thus extinguishing the nuclear reaction. The reactor building has a ventilation

  16. 3 D flow computations under a reactor vessel closure head

    International Nuclear Information System (INIS)

    Daubert, O.; Bonnin, O.; Hofmann, F.; Hecker, M.

    1995-12-01

    The flow under a vessel cover of a pressurised water reactor is investigated by using several computations and a physical model. The case presented here is turbulent, isothermal and incompressible. Computations are made with N3S code using a k-epsilon model. Comparisons between numerical and experimental results are on the whole satisfying. Some local improvements are expected either with more sophisticated turbulence models or with mesh refinements automatically computed by using the adaptive meshing technique which has been just implemented in N3S for 3D cases. (authors). 6 refs., 7 figs

  17. Internet accessible hot cell with gamma spectroscopy at the Missouri S and T nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Grant, Edwin [Nuclear Engineering, Missouri University of Science and Technology, 203 Fulton Hall, 300 W. 13th St., Rolla, MO 65409 (United States); Mueller, Gary, E-mail: gmueller@mst.edu [Nuclear Engineering, Missouri University of Science and Technology, 203 Fulton Hall, 300 W. 13th St., Rolla, MO 65409 (United States); Castano, Carlos; Usman, Shoaib; Kumar, Arvind [Nuclear Engineering, Missouri University of Science and Technology, 203 Fulton Hall, 300 W. 13th St., Rolla, MO 65409 (United States)

    2011-08-15

    Highlights: > A dual-chambered internet-accessible heavily shielded facility has been built. > The facility allows distance users to analyze neutron irradiated samples remotely. > The Missouri S and T system uses computer automation with user feedback. > The system can analyze multiple samples and assist several researchers concurrently. - Abstract: A dual-chambered internet-accessible heavily shielded facility with pneumatic access to the University of Missouri Science and Technology (Missouri S and T) 200 kW Research Nuclear Reactor (MSTR) core has been built and is currently available for irradiation and analysis of samples. The facility allows authorized distance users engaged in collaborative activities with Missouri S and T to remotely manipulate and analyze neutron irradiated samples. The system consists of two shielded compartments, one for multiple sample storage, and the other dedicated exclusively for radiation measurements and spectroscopy. The second chamber has multiple detector ports, with graded shielding, and has the capability to support gamma spectroscopy using radiation detectors such as an HPGe detector. Both these chambers are connected though a rapid pneumatic system with access to the MSTR nuclear reactor core. This new internet-based system complements the MSTR's current bare pneumatic tube (BPT) and cadmium lined pneumatic tube (CPT) facilities. The total transportation time between the core and the hot cell, for samples weighing 10 g, irradiated in the MSTR core, is roughly 3.0 s. This work was funded by the DOE grant number DE-FG07-07ID14852 and expands the capabilities of teaching and research at the MSTR. It allows individuals who do not have on-site access to a nuclear reactor facility to remotely participate in research and educational activities.

  18. InterProScan Result: FS932451 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS932451 FS932451_2_ORF2 773A43AAFA4CCB66 PANTHER PTHR10082 INTEGRIN BETA SUBUNIT 7e-07 T IPR001169 Integri...atrix adhesion (GO:0007160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  19. InterProScan Result: FS892858 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS892858 FS892858_4_ORF2 0C92A671D1557189 PFAM PF00995 Sec1 1.1e-50 T IPR001619 Sec1-like protein Biological... Process: vesicle docking involved in exocytosis (GO:0006904)|Biological Process: vesicle-mediated transport (GO:0016192) ...

  20. InterProScan Result: FS779843 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS779843 FS779843_4_ORF1 437F417A972B5635 PFAM PF04615 Utp14 6.5e-33 T IPR006709 Small-subunit process...ome, Utp14 Biological Process: rRNA processing (GO:0006364)|Cellular Component: small-subunit processome (GO:0032040) ...

  1. InterProScan Result: FS916423 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS916423 FS916423_2_ORF2 B2940816BE6DE7BE PFAM PF04615 Utp14 2.7e-61 T IPR006709 Small-subunit process...ome, Utp14 Biological Process: rRNA processing (GO:0006364)|Cellular Component: small-subunit processome (GO:0032040) ...

  2. InterProScan Result: FS898954 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS898954 FS898954_4_ORF2 AA99CAAFD037F5BB PFAM PF04615 Utp14 1.4e-56 T IPR006709 Small-subunit process...ome, Utp14 Biological Process: rRNA processing (GO:0006364)|Cellular Component: small-subunit processome (GO:0032040) ...

  3. Anaerobic Digestion of Sugarcane Vinasse Through a Methanogenic UASB Reactor Followed by a Packed Bed Reactor.

    Science.gov (United States)

    Cabrera-Díaz, A; Pereda-Reyes, I; Oliva-Merencio, D; Lebrero, R; Zaiat, M

    2017-12-01

    The anaerobic treatment of raw vinasse in a combined system consisting in two methanogenic reactors, up-flow anaerobic sludge blanket (UASB) + anaerobic packed bed reactors (APBR), was evaluated. The organic loading rate (OLR) was varied, and the best condition for the combined system was 12.5 kg COD m -3 day -1 with averages of 0.289 m 3 CH 4  kg COD r -1 for the UASB reactor and 4.4 kg COD m -3 day -1 with 0.207 m 3 CH 4  kg COD r -1 for APBR. The OLR played a major role in the emission of H 2 S conducting to relatively stable quality of biogas emitted from the APBR, with H 2 S concentrations <10 mg L -1 . The importance of the sulphate to COD ratio was demonstrated as a result of the low biogas quality recorded at the lowest ratio. It was possible to develop a proper anaerobic digestion of raw vinasse through the combined system with COD removal efficiency of 86.7% and higher CH 4 and a lower H 2 S content in biogas.

  4. PR-EDB: Power Reactor Embrittlement Database Version 3

    International Nuclear Information System (INIS)

    Wang, Jy-An John; Subramani, Ranjit

    2008-01-01

    The aging and degradation of light-water reactor pressure vessels is of particular concern because of their relevance to plant integrity and the magnitude of the expected irradiation embrittlement. The radiation embrittlement of reactor pressure vessel materials depends on many factors, such as neutron fluence, flux, and energy spectrum, irradiation temperature, and preirradiation material history and chemical compositions. These factors must be considered to reliably predict pressure vessel embrittlement and to ensure the safe operation of the reactor. Large amounts of data from surveillance capsules are needed to develop a generally applicable damage prediction model that can be used for industry standards and regulatory guides. Furthermore, the investigations of regulatory issues such as vessel integrity over plant life, vessel failure, and sufficiency of current codes, Standard Review Plans (SRPs), and Guides for license renewal can be greatly expedited by the use of a well-designed computerized database. The Power Reactor Embrittlement Database (PR-EDB) is such a comprehensive collection of data for U.S. designed commercial nuclear reactors. The current version of the PR-EDB lists the test results of 104 heat-affected-zone (HAZ) materials, 115 weld materials, and 141 base materials, including 103 plates, 35 forgings, and 3 correlation monitor materials that were irradiated in 321 capsules from 106 commercial power reactors. The data files are given in dBASE format and can be accessed with any personal computer using the Windows operating system. 'User-friendly' utility programs have been written to investigate radiation embrittlement using this database. Utility programs allow the user to retrieve, select and manipulate specific data, display data to the screen or printer, and fit and plot Charpy impact data. The PR-EDB Version 3.0 upgrades Version 2.0. The package was developed based on the Microsoft .NET framework technology and uses Microsoft Access for

  5. PR-EDB: Power Reactor Embrittlement Database - Version 3

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Jy-An John [ORNL; Subramani, Ranjit [ORNL

    2008-03-01

    The aging and degradation of light-water reactor pressure vessels is of particular concern because of their relevance to plant integrity and the magnitude of the expected irradiation embrittlement. The radiation embrittlement of reactor pressure vessel materials depends on many factors, such as neutron fluence, flux, and energy spectrum, irradiation temperature, and preirradiation material history and chemical compositions. These factors must be considered to reliably predict pressure vessel embrittlement and to ensure the safe operation of the reactor. Large amounts of data from surveillance capsules are needed to develop a generally applicable damage prediction model that can be used for industry standards and regulatory guides. Furthermore, the investigations of regulatory issues such as vessel integrity over plant life, vessel failure, and sufficiency of current codes, Standard Review Plans (SRPs), and Guides for license renewal can be greatly expedited by the use of a well-designed computerized database. The Power Reactor Embrittlement Database (PR-EDB) is such a comprehensive collection of data for U.S. designed commercial nuclear reactors. The current version of the PR-EDB lists the test results of 104 heat-affected-zone (HAZ) materials, 115 weld materials, and 141 base materials, including 103 plates, 35 forgings, and 3 correlation monitor materials that were irradiated in 321 capsules from 106 commercial power reactors. The data files are given in dBASE format and can be accessed with any personal computer using the Windows operating system. "User-friendly" utility programs have been written to investigate radiation embrittlement using this database. Utility programs allow the user to retrieve, select and manipulate specific data, display data to the screen or printer, and fit and plot Charpy impact data. The PR-EDB Version 3.0 upgrades Version 2.0. The package was developed based on the Microsoft .NET framework technology and uses Microsoft Access for

  6. Office for Analysis and Evaluation of Operational Data 1996 annual report. Volume 10, Number 1: Reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    This annual report of the US Nuclear Regulatory Commission`s Office for Analysis and Evaluation of Operational Data (AEOD) describes activities conducted during 1996. The report is published in three parts. NUREG-1272, Vol. 10, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports and reports to the NRC`s Operations Center. NUREG-1272, Vol. 10, No. 2, covers nuclear materials and presents a review of the events and concerns during 1996 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Both reports also contain a discussion of the Incident Investigation Team program and summarize both the Incident Investigation Team and Augmented Inspection Team reports. Each volume contains a list of the AEOD reports issued from CY 1980 through 1996. NUREG-1272, Vol. 10, No. 3, covers technical training and presents the activities of the Technical Training Center in support of the NRC`s mission in 1996.

  7. Sub-100 fs high average power directly blue-diode-laser-pumped Ti:sapphire oscillator

    Science.gov (United States)

    Rohrbacher, Andreas; Markovic, Vesna; Pallmann, Wolfgang; Resan, Bojan

    2016-03-01

    Ti:sapphire oscillators are a proven technology to generate sub-100 fs (even sub-10 fs) pulses in the near infrared and are widely used in many high impact scientific fields. However, the need for a bulky, expensive and complex pump source, typically a frequency-doubled multi-watt neodymium or optically pumped semiconductor laser, represents the main obstacle to more widespread use. The recent development of blue diodes emitting over 1 W has opened up the possibility of directly diode-laser-pumped Ti:sapphire oscillators. Beside the lower cost and footprint, a direct diode pumping provides better reliability, higher efficiency and better pointing stability to name a few. The challenges that it poses are lower absorption of Ti:sapphire at available diode wavelengths and lower brightness compared to typical green pump lasers. For practical applications such as bio-medicine and nano-structuring, output powers in excess of 100 mW and sub-100 fs pulses are required. In this paper, we demonstrate a high average power directly blue-diode-laser-pumped Ti:sapphire oscillator without active cooling. The SESAM modelocking ensures reliable self-starting and robust operation. We will present two configurations emitting 460 mW in 82 fs pulses and 350 mW in 65 fs pulses, both operating at 92 MHz. The maximum obtained pulse energy reaches 5 nJ. A double-sided pumping scheme with two high power blue diode lasers was used for the output power scaling. The cavity design and the experimental results will be discussed in more details.

  8. Calculations of resonances parameters for the ((2s2) 1Se, (2s2p) 1,3P0) and ((3s2) 1Se, (3s3p) 1,3P0) doubly excited states of helium-like ions with Z≤10 using a complex rotation method implemented in Scilab

    International Nuclear Information System (INIS)

    Gning, Youssou; Sow, Malick; Traoré, Alassane; Dieng, Matabara; Diakhate, Babacar; Biaye, Mamadi; Wagué, Ahmadou

    2015-01-01

    In the present work a special computational program Scilab (Scientific Laboratory) in the complex rotation method has been used to calculate resonance parameters of ((2s 2 ) 1 S e , (2s2p) 1,3 P 0 ) and ((3s 2 ) 1 S e , (3s3p) 1,3 P 0 ) states of helium-like ions with Z≤10. The purpose of this study required a mathematical development of the Hamiltonian applied to Hylleraas wave function for intrashell states, leading to analytical expressions which are carried out under Scilab computational program. Results are in compliance with recent theoretical calculations. - Highlights: • Resonance energy and widths computed for doubly excited states of helium-like ions. • Well-comparable results to the theoretical literature values up to Z=10. • Satisfactory agreements with theoretical calculations for widths

  9. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 15, 2011, 10:30 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du mardi 15 mars 2011 a 10h30

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 15, 2011, at 10:30 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  10. Safety evaluation report by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission for U.S. Energy Research and Development Administration Light Water Breeder Reactor. Special project No. 561

    International Nuclear Information System (INIS)

    1976-07-01

    The Safety Evaluation Report is presented for the Light Water Breeder Reactor (LWBR). The LWBR core is to be installed in the Shippingport reactor at the Shippingport Atomic Power Station. The Safety Evaluation Report is the result of an NRC staff review of the LWBR Safety Analysis Report submitted by the Division of Naval Reactors, U. S. Energy Research and Development Administration. As a result of its review, the NRC staff has recommended that: (1) a diverse trip signal, such as containment high pressure, be included in a 2-out-of-3 logic for initiation of safety injection; (2) power be locked out from the pressurizer surge isolation valve during normal operation; and (3) a chlorine monitor be installed in the main control room

  11. InterProScan Result: FS932793 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS932793 FS932793_2_ORF2 6EA452AE762D110F PANTHER PTHR12479 LYSOSOMAL-ASSOCIATED TRANSME...MBRANE PROTEIN 4.4e-71 T IPR004687 Golgi 4-transmembrane spanning transporter Biological Process: transport (GO:0006810)|Cellular Component: integral to membrane (GO:0016021) ...

  12. InterProScan Result: FS898120 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS898120 FS898120_5_ORF2 88A0F99A1A469778 PFAM PF03998 Utp11 6.1e-69 T IPR007144 Small-subunit process...ome, Utp11 Biological Process: rRNA processing (GO:0006364)|Cellular Component: small-subunit processome (GO:0032040) ...

  13. Manufacture of rings of 08Kh18N10T sheet for internal structures of WWER type reactors

    International Nuclear Information System (INIS)

    Fojta, A.; Nitka, B.

    1984-01-01

    Technology is presented of the manufacture of rings for the jacket, shaft, core catcher and shaft bottom of WWER-440 reactors produced by Vitkovice Steel Works. The rings are manufactured from sheets of austenitic steel 08Kh18N10T. The materials and technology problems are discussed of sheet production, ring welding technology and annealing following welding. The plastic properties are assessed of the welded joints and problems are outlined of ring production for WWER-1000 reactors. (B.S.)

  14. Principle tests of reactor pumped laser of 3He-Ar-Xe system

    International Nuclear Information System (INIS)

    Chen Hande; Jin Xingxing; Yang Chengde

    1994-01-01

    A nuclear reactor-pumped laser was demonstrated firstly by using the 3 He(P,n) 3 H reaction to excite a 3 He-Ar-Xe laser. Lasing was observed on the 1.73 μm (5d (3/2) 1 -6p(5/2) 1 transition) in Xe I. The CAEP Pulsed Reactor (CFBR-II) was used as a source of fast neutrons moderated by a 50 mm thick polyethylene sleeve around the laser cell. A laser cell was constructed from K 9 glass tubing 600 mm long and Φ34 mm with each end cut at Brewster's angle (quartz). The laser cell was baked out to 10 -3 Pa prior to filling with research-grade mixture ( 3 He/Ar/Xe = 34.7: 34.7: 0.267 kPa). A dielectric-coated 2 m radius-curvature back mirror (99.7% reflectivity at 1.73 μm) and a flat output coupler (Φ30 mm) were used to form the optical cavity. The cavity optics were placed outside the cell as shown in Fig.3. A schematic of the experimental configuration is shown. Typical laser signals obtained with the Ge detector (-80 degree C) are also shown. Laser output lags the fast neutron pulse by the neutron thermalization time (∼278 μs). The observed light output was shown to be caused by stimulated emission, because the signal disappeared when the reflecting (flat) mirror was covered. This precludes the possibility that the phenomenon was the result of γ-radiation interaction with the detector or the air in the light path. The measured laser energy was 80 times the maximum possible fluorescence energy. The observed wavelength was measured to be 1.73 μm by using glass filters. Laser output duration was approximately 735 μs

  15. Emissions of PCDD/Fs in flue gas from a medical waste incinerator in Shanghai

    Science.gov (United States)

    He, Jiao; Liu, Tao; Qiang, Ning; Li, Zhaohai; Cao, Yiqi; Xie, Li; Zhao, Yuanchen

    2017-12-01

    Emission characteristics of polychlorinated dibenzo-p-dioxins and polychlorinated dibenzofurans (PCDD/Fs) and 17 congeners from a medical waste incineration plants in Shanghai, China were investigated. Results showed that the dioxin concentration ranged from 5.0 to 23.3ng I-TEQ (Toxic Equivalent Quantity) Nm-3 under normal combustion concentration. The high dioxin incidence area was found in the boiler outlet and the bag filter inlet, and over 95% of the dioxins were present in the gaseous state. Polychlorinated dibenzofurans (PCDFs) accounted for a higher proportion of the total amount of PCDD/Fs than polychlorinated dibenzo-p-dioxins (PCDDs).

  16. Prevention of PCDD/Fs emission from a municipal wastewater sludge incinerator through enhanced control of copper aerosol

    Directory of Open Access Journals (Sweden)

    Peña, E.

    2012-10-01

    Full Text Available Municipal wastewater sludge incineration (MWSI leads to products of incomplete combustion, including chlorinated species such as dioxins and furans (PCDD/Fs. Other pollutants, such as heavy metals (HM, are released too as a consequence of feed traces, which depend on the specific activities of each area. The main aim of this work is to determine whether the early separation of the potential catalysts on the PCDD/Fs formation –HM as copper or zinc– offers a promising way to prevent the emission of these trace pollutants, considering that the current end-of-pipe measures don’t ensure their stable emission. Experimental results cover the size distributed target metal contents along the incineration line. These results show a high concentration of copper in the most penetrating aerosol size range of the electrostatic precipitator (0.6 μm - 1.0 μm, and how low emission values of both, total and metallic aerosol (mass basis, are compatible with irregular and unexplained outliers of PCDD/Fs emission.

    La incineración de lodos de aguas residuales urbanas acarrea la formación de compuestos derivados de combustiones incompletas, incluyendo especies cloradas como dioxinas y furanos (PCDD/Fs. Otros contaminantes, como metales pesados, se emiten como consecuencia de las trazas del lodo, las cuales dependen de las actividades del entorno. El objetivo principal es determinar si la separación de catalizadores potenciales en reacciones de formación de PCDD/Fs (cobre o zinc puede abrir vías para prevenir la emisión de contaminantes traza, considerando que ninguna de las técnicas de prevención actuales aseguran emisiones estables de metales pesados o PCDD/Fs. Se determinan concentraciones de metales pesados segregados por tamaño de partícula a lo largo de la línea de incineración. Los resultados muestran concentraciones elevadas de cobre en el aerosol de máxima penetración del electrofiltro (0,6 μm - 1,0 μm, y cómo concentraciones

  17. Safety report on WWR-S reactor

    International Nuclear Information System (INIS)

    Horyna, J.; Kaisler, L.; Listik, E.

    1981-04-01

    The present Safety Report of the WWR-S reactor summarizes findings obtained during the trial and partially also permanent operation of the reactor after two stages of its reconstruction implemented between 1974 and 1976. Most data are presented necessary for assessing probable risks of possible accident conditions whose consequences pose health hazards to individuals of the population, radiation personnel and the facilities themselves. Attention is devoted to the description of the locality, to components and systems, heat removal from the core, design aspects, the quality of new and old parts of the technological circuits, the systems of protection and control, the emergency core cooling system, the problems of radiation safety, and to the safety analyses of the abnormal states envisaged. The Report was compiled with regard to IAEA and CMEA recommendations concerning safe operation of research reactors and to the recommendations and binding decisions of the Czechoslovak Atomic Energy Commission. (author)

  18. Spent nuclear fuel discharges from U.S. reactors 1994

    International Nuclear Information System (INIS)

    1996-02-01

    Spent Nuclear Fuel Discharges from US Reactors 1994 provides current statistical data on fuel assemblies irradiated at commercial nuclear reactors operating in the US. This year's report provides data on the current inventories and storage capacities at these reactors. Detailed statistics on the data are presented in four chapters that highlight 1994 spent fuel discharges, storage capacities and inventories, canister and nonfuel component data, and assembly characteristics. Five appendices, a glossary, and bibliography are also included. 10 figs., 34 tabs

  19. Multiple ionization of argon under 123 eV FEL radiation and the creation of 3s-hollow ions

    International Nuclear Information System (INIS)

    Karamatskos, E T; Markellos, D; Lambropoulos, P

    2013-01-01

    We present calculations on the multiple ionization of argon at the photon energy 123 eV and pulse duration 50 fs. At that photon energy, it is possible to drive the two-photon resonant Auger transition 2p → 4p, whose lifetime is 5.5 fs, much shorter than the pulse duration. The excitation of a 2p electron to the 4p state thus creates a hole which decays by an Auger process. We have also included above-threshold ionization from the outer shells of the neutral and singly ionized species, which becomes significant at intensities of the order of ∼10 15 W cm −2 and higher. The populations of the various ionic species were obtained through the solution of the kinetic equations governing their production and decay during the pulse. The effect of the intensity distribution in the interaction volume has also been evaluated. We have further shown that doubly hollow ionic states of the type 3s 0 3p n with 2 ⩽ n ⩽ 6 are created, which can decay only via spontaneous emission, with lifetimes orders of magnitude longer than the pulse duration. These hollow-ion states can potentially serve as a starting point for a variety of experimental investigations on doubly excited states. (paper)

  20. Differentiation between grade 3 and grade 4 articular cartilage defects of the knee: Fat-suppressed proton density-weighted versus fat-suppressed three-dimensional gradient-echo MRI

    Energy Technology Data Exchange (ETDEWEB)

    Lee, So Yeon; Jee, Won-Hee; Kim, Sun Ki (Dept. of Radiology, Seoul St Mary' s Hospital, Catholic Univ. of Korea, Seoul (Korea)), e-mail: whjee@catholic.ac.kr; Koh, In-Jun (Dept. of Joint Reconstruction Center, Seoul National Univ. Bundang Hospital, Seoul (Korea)); Kim, Jung-Man (Dept. of Orthopedic Surgery, Seoul St Mary' s Hospital, Catholic Univ. of Korea, Seoul (Korea))

    2010-05-15

    Background: Fat-suppressed (FS) proton density (PD)-weighted magnetic resonance imaging (MRI) and FS three-dimensional (3D) gradient-echo imaging such as spoiled gradient-recalled (SPGR) sequence have been established as accurate methods for detecting articular cartilage defects. Purpose: To retrospectively compare the diagnostic efficacy between FS PD-weighted and FS 3D gradient-echo MRI for differentiating between grade 3 and grade 4 cartilage defects of the knee with arthroscopy as the standard of reference. Material and Methods: Twenty-one patients who had grade 3 or 4 cartilage defects in medial femoral condyle at arthroscopy and knee MRI were included in this study: grade 3, >50% cartilage defects; grade 4, full thickness cartilage defects exposed to the bone. Sagittal FS PD-weighted MR images and FS 3D gradient-echo images with 1.5 T MR images were independently graded for the cartilage abnormalities of medial femoral condyle by two musculoskeletal radiologists. Statistical analysis was performed by Fisher's exact test. Inter-observer agreement in grading of cartilage was assessed using ? coefficients. Results: Arthroscopy revealed grade 3 defects in 17 patients and grade 4 defects in 4 patients in medial femoral condyles. For FS 3D gradient-echo images grade 3 defects were graded as grade 3 (n=15) and grade 4 (n=2), and all grade 4 defects (n=4) were correctly graded. However, for FS PD-weighted MR images all grade 3 defects were misinterpreted as grade 1 (n=1) and grade 4 (n=16), whereas all grade 4 defects (n=4) were correctly graded. FS 3D gradient-echo MRI could differentiate grade 3 from grade 4 defects (P=0.003), whereas FS PD-weighted imaging could not (P=1.0). Inter-observer agreement was substantial (?=0.70) for grading of cartilage using FS PD-weighted imaging, whereas it was moderate (?=0.46) using FS 3D gradient-echo imaging. Conclusion: FS 3D gradient-echo MRI is more helpful for differentiating between grade 3 and grade 4 cartilage

  1. In-pile creep test technique for zirconium alloys examination in BR-10 reactor channels

    International Nuclear Information System (INIS)

    Pevchikh, Yu.M.; Kruglov, A.S.; Troyanov, V.M.

    2002-01-01

    The irradiation enhanced creep phenomenon was discovered in stainless steels as a specific physical process accompanying high-intensity neutron flux irradiation in fast reactors. IPPE is also experienced in irradiation creep test activities, studying different types of materials under irradiation in BR-10 fast reactor. Series of in-channel type test facilities were constructed and tested in BR-10 reactor's 'dry' channels in order to carry out full-scale instrumented examination regarded to in-pile creep behaviour of different reactor materials. As a result, a specific test technique, named 'Tensometric method', has been developed and experimentally proved to be power enough in order to investigate irradiation creep of materials right in situ under neutron irradiation. The main peculiarity of test facility, which is constructed to apply the tensometric method, consists in absence of any special deformation-measurement cell at all. The in-pile creep strain measurement technique developed at IPPE is based on the non-direct measurement of specimen's deformation (either linear tensile strain or angular twisting one), which directly affects the loaded draws' tension parameters. Starting from 1993, in-pile creep experiments to investigate in-reactor creep behaviour of E110 and E635 zirconium alloys were carried out in BR-10. Experimental results and data collected during more than 20-year of BR-10 in-reactor creep test experience can be assumed as a strong evidence that the tensometric technique is a powerful instrument, which can give a chance to study different irradiation effects on reactor materials directly under irradiation. (author)

  2. Dry Eye Disease following Refractive Surgery: A 12-Month Follow-Up of SMILE versus FS-LASIK in High Myopia

    Science.gov (United States)

    Wang, Bingjie; Chu, Renyuan; Dai, Jinhui; Qu, Xiaomei; Zhou, Hao

    2015-01-01

    Purpose. To compare dry eye disease following SMILE versus FS-LASIK. Design. Prospective, nonrandomised, observational study. Patients. 90 patients undergoing refractive surgery for myopia were included. 47 eyes underwent SMILE and 43 eyes underwent FS-LASIK. Methods. Evaluation of dry eye disease was conducted preoperatively and at 1, 3, 6, and 12 months postoperatively, using the Salisbury Eye Evaluation Questionnaire (SEEQ) and TBUT. Results. TBUT reduced following SMILE at 1 and 3 months (p dry eye disease than FS-LASIK at 6 months postoperatively but demonstrates similar degrees of dry eye disease at 12 months. PMID:26649190

  3. Small Incision Lenticule Extraction (SMILE versus Femtosecond Laser-Assisted In Situ Keratomileusis (FS-LASIK for Myopia: A Systematic Review and Meta-Analysis.

    Directory of Open Access Journals (Sweden)

    Zeren Shen

    Full Text Available The goal of this study was to compare small incision lenticule extraction (SMILE with femtosecond laser-assisted in situ keratomileusis (FS-LASIK for treating myopia.The CENTRAL, EMBASE, PubMed databases and a Chinese database (SinoMed were searched in May of 2016. Twelve studies with 1,076 eyes, which included three randomized controlled trials (RCTs and nine cohorts, met our inclusion criteria. The overall quality of evidence was evaluated using the Grading of Recommendations Assessment, Development and Evaluation (GRADE working group framework. Data were extracted and analysed at three to six months postoperatively. Primary outcome measures included a loss of one or more lines of best spectacle corrected visual acuity (BSCVA, uncorrected visual acuity (UCVA of 20/20 or better, mean logMAR UCVA, postoperative mean spherical equivalent (SE and postoperative refraction within ±1.0 D of the target refraction. Secondary outcome measures included ocular surface disease index (OSDI, tear breakup time (TBUT and Schirmer's 1 test (S1T as dry eye parameters, along with corneal sensitivity.The overall quality of evidence was considered to be low to very low. Pooled results revealed no significant differences between the two groups with regard to a loss of one or more lines in the BSCVA (OR 1.71; 95% CI: 0.81, 3.63; P = 0.16, UCVA of 20/20 or better (OR 0.71; 95% CI: 0.44, 1.15; P = 0.16, logMAR UCVA (MD 0.00; 95% CI: -0.03, 0.04; P = 0.87, postoperative refractive SE (MD -0.00; 95% CI: -0.05, 0.05; P = 0.97 or postoperative refraction within ±1.0 D of the target refraction (OR 0.78; 95% CI: 0.22, 2.77; P = 0.70 within six months postoperatively. The pooled analysis also indicated that the FS-LASIK group suffered more severely from dry eye symptoms (OSDI; MD -6.68; 95% CI: -11.76, -2.00; P = 0.006 and lower corneal sensitivity (MD 12.40; 95% CI: 10.23, 14.56; P < 0.00001 at six months postoperatively.In conclusion, both FS-LASIK and SMILE are safe

  4. A Temperature Dependent Lumped-charge Model for Trench FS-IGBT

    DEFF Research Database (Denmark)

    Duan, Yaoqiang; Kang, Yong; Iannuzzo, Francesco

    2018-01-01

    Abstract: This paper proposes a temperature dependent lumped-charge model for FS-IGBT. Due to the evolution of the IGBT structure, the existing lumped-charge IGBT model established for NPT-IGBT is not suitable for the simulation of FS-IGBT. This paper extends the lumped-charge IGBT model including...... the field-stop (FS) structure and temperature characteristics. The temperature characteristics of the model are considered for both the bipolar part and unipolar part. In addition, a new PN junction model which can distinguish the collector structure is presented and validated by TCAD simulation. Finally...

  5. [Molecular pathogenesis of Waardenburg syndrome type II resulting from SOX10 gene mutation].

    Science.gov (United States)

    Zhang, Hua; Chen, Hongsheng; Feng, Yong; Qian, Minfei; Li, Jiping; Liu, Jun; Zhang, Chun

    2016-08-01

    To explore the molecular mechanism of Waardenburg syndrome type II (WS2) resulting from SOX10 gene mutation E248fs through in vitro experiment. 293T cells were transiently transfected with wild type (WT) SOX10 and mutant type (MT) E248fs plasmids. The regulatory effect of WT/MT SOX10 on the transcriptional activity of MITF gene and influence of E248fs on WT SOX10 function were determined with a luciferase activity assay. The DNA binding capacity of the WT/MT SOX10 with the promoter of the MITF gene was determined with a biotinylated double-stranded oligonucleotide probe containing the SOX10 binding sequence cattgtc to precipitate MITF and E248fs, respectively. The stability of SOX10 and E248fs were also analyzed. As a loss-of-function mutation, the E248fs mutant failed to transactivate the MITF promoter as compared with the WT SOX10 (P<0.01), which also showed a dominant-negative effect on WT SOX10. The WT SOX10 and E248fs mutant were also able to bind specifically to the cattgtc motif in the MITF promoter, whereas E248fs had degraded faster than WT SOX10. Despite the fact that the E248fs has a dominant-negative effect on SOX10, its reduced stability may down-regulate the transcription of MITF and decrease the synthesis of melanin, which may result in haploinsufficiency of SOX10 protein and cause the milder WS2 phenotype.

  6. Sensitivity analysis of reflector types and impurities in a 10 MW MTR type nuclear research reactor

    International Nuclear Information System (INIS)

    Khattab, K.; Khamis, I.

    2008-01-01

    The 2-D and 3-D neutronics models for 10 MW nuclear research reactor of MTR type have been developed and presented in this paper. Our results agree very well with the results of seven countries mentioned in the IAEA-TECDOC-233. To study the effect of reflector types on the reactor effective multiplication factor, five types of reflectors such as pure beryllium, beryllium, heavy water, carbon and water are selected for this study. The pure beryllium is found to be the most efficient reflector in this group. The effect of the most important impurities, which exist on the beryllium reflector such as iron, silicon and aluminium on the reactor multiplication factor, have been analyzed as well. It is found that the iron impurity affects the reactor multiplication factor the most compared to silicon and aluminium impurities. (author)

  7. Emission profiles of polychlorinated dibenzodioxins, polychlorinated dibenzofurans (PCDD/Fs), dioxin-like PCBs and hexachlorobenzene (HCB) from secondary metallurgy industries in Portugal.

    Science.gov (United States)

    Antunes, Pedro; Viana, Paula; Vinhas, Tereza; Rivera, J; Gaspar, Elvira M S M

    2012-09-01

    This paper reports, for the first time, a study of dioxin emissions from 10 siderurgies and metallurgies, secondary copper, aluminum and lead metallurgies, in Portugal. The study reports the emission factors and total emission amounts of PCDD/Fs, dioxin-like PCBs and hexachlorobenzene (HCB). The congener patterns were characterized and are discussed. The results showed that the total amount of PCDFs is higher than PCDDs in flue gas of each industrial unit. The toxic equivalent emission factors of pollutants emitted are 3098-3338 ngI-TEQt(-1) for PCDD/Fs and 597-659 ng I-TEQt(-1) for dioxin-like PCBs in siderurgies production (total estimated emission amounts released to atmosphere of 3.9-4.5 g I-TEQyr(-1)), 50-152 ng I-TEQt(-1) for PCDD/Fs and 24-121 ng I-TEQt(-1) for dioxin-like PCBs in ferrous foundries production (total estimated emission amounts released to atmosphere of 0.0010-0.0016 g I-TEQyr(-1)) and 5.8-5715 ng I-TEQt(-1) for PCDD/Fs and 0.49-259 ng I-TEQt(-1) for dioxin-like PCBs in non-ferrous foundries production (total estimated emission amounts released to atmosphere of 0.00014-0.12 g I-TEQyr(-1)). The HCB emission from siderurgies production is 0.94-3.2 mg t(-1) (total estimated emission amounts released 0.94-3.8 g yr(-1)), being much smaller, residual, in the emissions of the other types of plants (0.0012-0.026 mg t(-1) production and total estimated emission amounts released to atmosphere of 0.013-1.7 mg yr(-1)). Copyright © 2012 Elsevier Ltd. All rights reserved.

  8. Revised reactor accident source terms in the U.S. and implementation for light water reactors

    International Nuclear Information System (INIS)

    Soffer, L.; Lee, J.Y.

    1992-01-01

    Current NRC reactor accident source terms used for licensing are contained in Regulatory Guides 1.3 and 1.4 and specify that 100 % of the core inventory of noble gases and 25 % of the iodine fission products are assumed to be instantaneously available for release from the containment. The chemical form of the iodine fission products is also assumed to be predominantly elemental (I 2 ) iodine. These assumptions have strongly affected present nuclear plant designs. Severe accident research results have confirmed that although the current source term is very substantial and has resulted in a very high level of plant capability, the present source term is no longer compatible with a realistic understanding of severe accidents. The NRC has issued a proposed revision of the reactor accident source terms as part of several regulatory activities to incorporate severe accident insights for future plants. A revision to 10 CFR 100 is also being proposed to specify site criteria directly and to eliminate source terms and doses for site evaluation. Reactor source terms will continue to be important in evaluating plant designs. Although intended primarily for future plants, existing and evolutionary power plants may voluntarily apply revised accident source term insights as well in licensing. The proposed revised accident source terms are presented in terms of fission product composition, magnitude, timing and iodine chemical form. Some implications for light water reactors are discussed. (author)

  9. Internet accessible hot cell with gamma spectroscopy at the Missouri S and T nuclear reactor

    International Nuclear Information System (INIS)

    Grant, Edwin; Mueller, Gary; Castano, Carlos; Usman, Shoaib; Kumar, Arvind

    2011-01-01

    Highlights: → A dual-chambered internet-accessible heavily shielded facility has been built. → The facility allows distance users to analyze neutron irradiated samples remotely. → The Missouri S and T system uses computer automation with user feedback. → The system can analyze multiple samples and assist several researchers concurrently. - Abstract: A dual-chambered internet-accessible heavily shielded facility with pneumatic access to the University of Missouri Science and Technology (Missouri S and T) 200 kW Research Nuclear Reactor (MSTR) core has been built and is currently available for irradiation and analysis of samples. The facility allows authorized distance users engaged in collaborative activities with Missouri S and T to remotely manipulate and analyze neutron irradiated samples. The system consists of two shielded compartments, one for multiple sample storage, and the other dedicated exclusively for radiation measurements and spectroscopy. The second chamber has multiple detector ports, with graded shielding, and has the capability to support gamma spectroscopy using radiation detectors such as an HPGe detector. Both these chambers are connected though a rapid pneumatic system with access to the MSTR nuclear reactor core. This new internet-based system complements the MSTR's current bare pneumatic tube (BPT) and cadmium lined pneumatic tube (CPT) facilities. The total transportation time between the core and the hot cell, for samples weighing 10 g, irradiated in the MSTR core, is roughly 3.0 s. This work was funded by the DOE grant number DE-FG07-07ID14852 and expands the capabilities of teaching and research at the MSTR. It allows individuals who do not have on-site access to a nuclear reactor facility to remotely participate in research and educational activities.

  10. InterProScan Result: FS836461 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS836461 FS836461_6_ORF1 4B253188815CBC36 PRINTS PR00385 P450 2.2e-08 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  11. InterProScan Result: FS858611 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS858611 FS858611_5_ORF1 E15CFA5CC72259B8 PRINTS PR00385 P450 7.7e-06 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  12. InterProScan Result: FS793798 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS793798 FS793798_2_ORF2 AF822AAC581E0462 PFAM PF00067 p450 1.8e-29 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  13. InterProScan Result: FS764425 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS764425 FS764425_1_ORF2 38B2ED93758BCB7B PFAM PF00067 p450 4.2e-24 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  14. InterProScan Result: FS784665 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS784665 FS784665_4_ORF1 7E959D55ADFEC376 PRINTS PR00385 P450 5.5e-11 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  15. Development and applications of reactor noise analysis at Ontario Hydro`s CANDU reactors

    Energy Technology Data Exchange (ETDEWEB)

    Gloeckler, O [Ontario Hydro, Toronto, ON (Canada); Tulett, M V [Ontario Hydro, Pickering, ON (Canada). Pickering Generating Station

    1996-12-31

    In 1992 a program was initiated to establish reactor noise analysis as a practical tool for plant performance monitoring and system diagnostics in Ontario Hydro`s CANDU reactors. Since then, various CANDU-specific noise analysis applications have been developed and validated. The noise-based statistical techniques are being successfully applied as powerful troubleshooting and diagnostic tools to a wide variety of actual operational I and C problems. The dynamic characteristics of critical plant components, instrumentation and processes are monitored on a regular basis. Recent applications of noise analysis include (1) validating the dynamics of in-core flux detectors (ICFDS) and ion chambers, (2) estimating the prompt fraction ICFDs in noise measurements at full power and in power rundown tests, (3) identifying the cause of excessive signal fluctuations in certain flux detectors, (4) validating the dynamic coupling between liquid zone control signals, (5) detecting and monitoring mechanical vibrations of detector tubes induced by moderator flow, (6) estimating the dynamics and response time of RTD (Resistance Temperature Detector) temperature signals, (7) isolating the cause of RTD signal anomalies, (8) investigating the source of abnormal flow signal behaviour, (9) estimating the overall response time of flow and pressure signals, (10) detecting coolant boiling in fully instrumented fuel channels, (11) monitoring moderator circulation via temperature noise, and (12) predicting the performance of shut-off rods. Some of these applications are performed on an as-needed basis. The noise analysis program, in the Pickering-B station alone, has saved Ontario Hydro millions of dollars during its first three years. The results of the noise analysis program have been also reviewed by the regulator (Atomic Energy Control Board of Canada) with favorable results. The AECB have expressed interest in Ontario Hydro further exploiting the use of noise analysis technology. (author

  16. Hybrid fs/ps CARS for Sooting and Particle-laden Flames

    Energy Technology Data Exchange (ETDEWEB)

    Hoffmeister, Kathryn N. Gabet; Guildenbecher, Daniel Robert; Kearney, Sean P.

    2015-12-01

    We report the application of ultrafast rotational coherent anti-Stokes Raman scattering (CARS) for temperature and relative oxygen concentration measurements in the plume emanating from a burning aluminized ammonium perchlorate propellant strand. Combustion of these metal-based propellants is a particularly hostile environment for laserbased diagnostics, with intense background luminosity, scattering and beam obstruction from hot metal particles that can be as large as several hundred microns in diameter. CARS spectra that were previously obtained using nanosecond pulsed lasers in an aluminumparticle- seeded flame are examined and are determined to be severely impacted by nonresonant background, presumably as a result of the plasma formed by particulateenhanced laser-induced breakdown. Introduction of fs/ps laser pulses enables CARS detection at reduced pulse energies, decreasing the likelihood of breakdown, while simultaneously providing time-gated elimination of any nonresonant background interference. Temperature probability densities and temperature/oxygen correlations were constructed from ensembles of several thousand single-laser-shot measurements from the fs/ps rotational CARS measurement volume positioned within 3 mm or less of the burning propellant surface. Preliminary results in canonical flames are presented using a hybrid fs/ps vibrational CARS system to demonstrate our progress towards acquiring vibrational CARS measurements for more accurate temperatures in the very high temperature propellant burns.

  17. Twenty years of Radiology in RP-10 nuclear reactor protection

    International Nuclear Information System (INIS)

    Zapata, Alejandro L.; Ramos, Fernando T.; Arrieta, Rolando W.B.; Vela Mora, Mariano

    2013-01-01

    In this report we present the results about radiation controls during 1990 - 2010, carried out in the Nuclear Reactor RP-10 of the Nuclear Center of Huarangal. These controls and radiological evaluation are of much utility for the radio personnel protection of this one and other reactors, since it allows to compares these variables with respect to the time. From the results obtained in monitoring and radiation controls, we conclude that in no case it has been reached the limits allowed by the Peruvian Regulating Authority. (author)

  18. Dynamics of TRIGA-3 Salazar Reactor.; Dinamica del Reactor TRIGA Mark III del Centro Nuclear de Mexico.

    Energy Technology Data Exchange (ETDEWEB)

    Gallardo S, L F

    1991-12-31

    The theoretical study of temporal behavior of a nuclear reactor is of great importance, since it allows to know, in advance, the conditions to which a reactor is going to be submitted. The reliability of two computer codes (AIREK-JEN and PLANKIN) designed to reproduce the temporal behavior of nuclear reactors, generally power reactors, when they are applied to reproduce the dynamic behavior of TRIGA-3 Salazar Reactor is analyzed. In the first chapters, the fundamental equations that solve this computer codes are deduced, and also the main characteristics of TRIGA-3 Salazar Reactor and the necessary data to run the programs are presented; later the results obtained with the computer codes and the experimental results reported in the operational logbook of the reactor are compared, with the result that such computer codes are applicable to the temporal study of TRIGA-3 Salazar Reactor. (Author).

  19. 3D CAD model of the subcritical nuclear reactor of IPN; Modelo CAD 3D del reactor nuclear subcritico del IPN

    Energy Technology Data Exchange (ETDEWEB)

    Pahuamba V, F. de J.; Delfin L, A.; Gomez T, A. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Ibarra R, G.; Del Valle G, E.; Sanchez R, A., E-mail: narehc@hotmail.com [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN, Edif. 9, Unidad Profesional Adolfo Lopez Mateos, San Pedro Zacatenco, 07738 Ciudad de Mexico (Mexico)

    2016-09-15

    The three-dimensional (3D) CAD model of the subcritical reactor Chicago model 9000 of Instituto Politecnico Nacional (IPN) allows obtaining a 3D view with the dimensions of each of its components, such as: natural uranium cylindrical rods, fuel elements, hexagonal reactor core arrangement, cylindrical stainless steel tank containing the core, fuel element support grids and reactor water cleaning system. As a starting point for the development of the model, the Chicago model 9000 subcritical reactor manual provided by the manufacturer was used, the measurement and verification of the components to adapt the geometric, physical and mechanical characteristics was carried out and materials standards were used to obtain a design that allows to elaborate a new manual according to the specifications. In addition, the 3D models of the building of the Advanced Physics Laboratory, neutron generator, cobalt source and the corridors connecting to the subcritical reactor facility were developed, allowing an animated ride, developed by computer-aided design software. The manual provided by the company Nuclear Chicago, dates from the year 1959 and presents diverse deviations in the design and dimensions of the reactor components. The model developed; in addition to supporting the development of the new manual represents a learning tool to visualize the reactor components. (Author)

  20. Towards a reverse Newman’s theorem in interactive information complexity

    Czech Academy of Sciences Publication Activity Database

    Brody, J.; Buhrman, H.; Koucký, Michal; Loff, B.; Speelman, F.; Vereshchagin, N.K.

    2016-01-01

    Roč. 76, č. 3 (2016), s. 749-781 ISSN 0178-4617 R&D Projects: GA AV ČR IAA100190902 Institutional support: RVO:67985840 Keywords : communication complexity * information complexity * information theory Subject RIV: BA - General Mathematics Impact factor: 0.735, year: 2016 http://link.springer.com/article/10.1007%2Fs00453-015-0112-9

  1. Towards a reverse Newman’s theorem in interactive information complexity

    Czech Academy of Sciences Publication Activity Database

    Brody, J.; Buhrman, H.; Koucký, Michal; Loff, B.; Speelman, F.; Vereshchagin, N.K.

    2016-01-01

    Roč. 76, č. 3 (2016), s. 749-781 ISSN 0178-4617 R&D Projects: GA AV ČR IAA100190902 Institutional support: RVO:67985840 Keywords : communication complexity * information complexity * information theory Subject RIV: BA - General Mathematics Impact factor: 0.735, year: 2016 http ://link.springer.com/article/10.1007%2Fs00453-015-0112-9

  2. Fast reactor safety testing in Transient Reactor Test (TREAT) in the 1980s

    International Nuclear Information System (INIS)

    Wright, A.E.; Dutt, D.S.; Harrison, L.J.

    1990-01-01

    Several series of fast reactor safety tests were performed in TREAT during the 1980s. These focused on the transient behavior of full-length oxide fuels (US reference, UK reference, and US advanced design) and on modern metallic fuels. Most of the tests addressed fuel behavior under transient overpower or loss-of-flow conditions. The test series were the PFR/TREAT tests; the RFT, TS, CDT, and RX series on oxide fuels; and the M series on metallic fuels. These are described in terms of their principal results and relevance to analyses and safety evaluation. 4 refs., 3 tabs

  3. Direct harvesting of Helium-3 (3He) from heavy water nuclear reactors

    International Nuclear Information System (INIS)

    Bentoumi, G.; Didsbury, R.; Jonkmans, G.; Rodrigo, L.; Sur, B.

    2013-01-01

    The thermal neutron activation of deuterium inside a heavy-water-moderated or -cooled nuclear reactor produces a build-up of tritium in the heavy water. The in situ decay of tritium can, for certain reactor types and operating conditions, produce potentially useable amounts of 3 He, which can be directly extracted via the heavy-water cover gas without first separating, collecting and storing tritium outside the reactor. It is estimated that the amount of 3 He available for recovery from the moderator cover gas of a 700 MWe class Pressurized Heavy Water Reactor (PHWR) ranges from 0.1 to 0.7 m 3 (STP) per annum, varying with the tritium activity buildup in the moderator. The harvesting of 3 He would generate approximately 12.7 m 3 (STP) of 3 He, worth more than $30M at current market rates, over a typical 25-year operating cycle of the PHWR. This paper discusses the production of 3 He in the moderator of a PHWR and its extraction from the 4 He moderator cover gas system using conventional methods. (author)

  4. U.S. Non-proliferation policy and programs regarding use of high-enriched uranium in research reactors

    International Nuclear Information System (INIS)

    Lewis, R.A.

    1993-01-01

    Uranium enriched to 90-93%, supplied by the U.S., is now used in 141 research and test reactors in 35 countries around the world with a cumulative power of 1714 mw. Since of the order of 3 kg of 235 U is involved annually in fuel fabrication, fresh fuel transport and storage, reactor operation, and spent fuel cooling and return per megawatt of research reactor power, it is estimated that more than 5000 kg of very high-enriched uranium is handled each year to operate these reactors. Recent U.S. assessments have led to the tentative conclusion that in only approximately 11 of these reactors, generally those of highest power or power density, is the use of 90-93% enriched uranium currently a technical necessity. Universal use of the best state-of-the-art fuel technology would permit an estimated 90 of these reactors to use 20% enriched fuel, and estimated 40 others to use 45% enriched fuel, without significant performance degradation. If advanced research reactor fuel development programs currently under way in the U.S. and elsewhere are successful, it may, in fact, be possible to operate virtually all of these reactors on less than 20% enriched uranium in the longer term. The physical and economic practicality of these developmental fuels must, of course, await future assessments

  5. Scale analysis of decay heat removal system between HTR-10 and HTR-PM reactors under accidental conditions

    International Nuclear Information System (INIS)

    Roberto, Thiago D.; Alvim, Antonio C.M.

    2017-01-01

    The 10 MW high-temperature gas-cooled test module (HTR-10) is a graphite-moderated and helium-cooled pebble bed reactor prototype that was designed to demonstrate the technical and safety feasibility of this type of reactor project under normal and accidental conditions. In addition, one of the systems responsible for ensuring the safe operation of this type of reactor is the passive decay heat removal system (DHRS), which operates using passive heat removal processes. A demonstration of the heat removal capacity of the DHRS under accidental conditions was analyzed based on a benchmark problem for design-based accidents on an HTR-10, i.e., the pressurized loss of forced cooling (PLOFC) described in technical reports produced by the International Atomic Energy Agency. In fact, the HTR-10 is also a proof-of-concept reactor for the high-temperature gas-cooled reactor pebble-bed module (HTR-PM), which generates approximately 25 times more heat than the HTR-10, with a thermal power of 250 MW, thereby requiring a DHRS with a higher system capacity. Thus, because an HTR-10 is a prototype reactor for an HTR-PM, a scaling analysis of the heat transfer process from the reactor to the DHRS was carried out between the HTR-10 and HTR-PM systems to verify the distortions of scale and the differences between the main dimensionless numbers from the two projects. (author)

  6. Scale analysis of decay heat removal system between HTR-10 and HTR-PM reactors under accidental conditions

    Energy Technology Data Exchange (ETDEWEB)

    Roberto, Thiago D.; Alvim, Antonio C.M. [Coordenacao de Pos-Graduacao e Pesquisa de Engenharia (PEN/COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear; Lapa, Celso M.F., E-mail: thiagodbtr@gmail.com, E-mail: lapa@ien.gov.br, E-mail: alvim@nuclear.ufrj.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    The 10 MW high-temperature gas-cooled test module (HTR-10) is a graphite-moderated and helium-cooled pebble bed reactor prototype that was designed to demonstrate the technical and safety feasibility of this type of reactor project under normal and accidental conditions. In addition, one of the systems responsible for ensuring the safe operation of this type of reactor is the passive decay heat removal system (DHRS), which operates using passive heat removal processes. A demonstration of the heat removal capacity of the DHRS under accidental conditions was analyzed based on a benchmark problem for design-based accidents on an HTR-10, i.e., the pressurized loss of forced cooling (PLOFC) described in technical reports produced by the International Atomic Energy Agency. In fact, the HTR-10 is also a proof-of-concept reactor for the high-temperature gas-cooled reactor pebble-bed module (HTR-PM), which generates approximately 25 times more heat than the HTR-10, with a thermal power of 250 MW, thereby requiring a DHRS with a higher system capacity. Thus, because an HTR-10 is a prototype reactor for an HTR-PM, a scaling analysis of the heat transfer process from the reactor to the DHRS was carried out between the HTR-10 and HTR-PM systems to verify the distortions of scale and the differences between the main dimensionless numbers from the two projects. (author)

  7. ''Sleeping reactor'' irradiations: Shutdown reactor determination of short-lived activation products

    International Nuclear Information System (INIS)

    Jerde, E.A.; Glasgow, D.C.

    1998-01-01

    At the High-Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory, the principal irradiation system has a thermal neutron flux (φ) of ∼ 4 x 10 14 n/cm 2 · s, permitting the detection of elements via irradiation of 60 s or less. Irradiations of 6 or 7 s are acceptable for detection of elements with half-lives of as little as 30 min. However, important elements such as Al, Mg, Ti, and V have half-lives of only a few minutes. At HFIR, these can be determined with irradiation times of ∼ 6 s, but the requirement of immediate counting leads to increased exposure to the high activity produced by irradiation in the high flux. In addition, pneumatic system timing uncertainties (about ± 0.5 s) make irradiations of 9 Be(γ,n) 8 Be, the gamma rays principally originating in the spent fuel. Upon reactor SCRAM, the flux drops to ∼ 1 x 10 10 n/cm 2 · s within 1 h. By the time the fuel elements are removed, the flux has dropped to ∼ 6 x 10 8 . Such fluxes are ideal for the determination of short-lived elements such as Al, Ti, Mg, and V. An important feature of the sleeping reactor is a flux that is not constant

  8. InterProScan Result: FS865512 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS865512 FS865512_4_ORF2 5E2A7F9124D73F34 PRINTS PR00385 P450 1.7e-09 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  9. InterProScan Result: FS804057 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS804057 FS804057_2_ORF1 F65DFC6DB9EB6E59 PFAM PF00067 p450 1.6e-13 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  10. InterProScan Result: FS783911 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS783911 FS783911_6_ORF1 F4FB77A4630C2DCB PRINTS PR00385 P450 8.8e-13 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  11. D-3He fuel cycles for neutron lean reactors

    International Nuclear Information System (INIS)

    Kernbichler, W.; Miley, G.H.; Heindler, M.

    1989-01-01

    The intrinsic potential of D-3He as a reactor fuel is investigated for a large range of 3He to D density ratios. A steady-state zero-dimensional reactor model is developed in which much care is attributed to a proper treatment of fast fusion products. Useful ranges of reactor parameters as well as temperature-density windows for driven and ignited operation are identified. Various figures of merit are calculated, such as power densities, net power production, neutron production, tritium load and radiative power. These results suggest several optimistic conclusions about the performance of D-3He as a reactor fuel

  12. Distinct chromatin environment associated with phosphorylated H3S10 histone during pollen mitosis I in orchids.

    Science.gov (United States)

    Sharma, Santosh Kumar; Yamamoto, Maki; Mukai, Yasuhiko

    2017-01-01

    Pollen developmental pathway in plants involving synchronized transferal of cellular divisions from meiosis (microsporogenesis) to mitosis (pollen mitosis I/II) eventually offers a unique "meiosis-mitosis shift" at pollen mitosis I. Since the cell type (haploid microspore) and fate of pollen mitosis I differ from typical mitosis (in meristem cells), it is immensely important to analyze the chromosomal distribution of phosphorylated H3S10 histone during atypical pollen mitosis I to comprehend the role of histone phosphorylation in pollen development. We investigated the chromosomal phosphorylation of H3S10 histone during pollen mitosis I in orchids using immunostaining technique. The chromosomal distribution of H3S10ph during pollen mitosis I revealed differential pattern than that of typical mitosis in plants, however, eventually following the similar trends of mitosis in animals where H3S10 phosphorylation begins in the pericentromeric regions first, later extending to the whole chromosomes, and finally declining at anaphase/early cytokinesis (differentiation of vegetative and generative cells). The study suggests that the chromosomal distribution of H3S10ph during cell division is not universal and can be altered between different cell types encoded for diverse cellular processes. During pollen development, phosphorylation of histone might play a critical role in chromosome condensation events throughout pollen mitosis I in plants.

  13. Relevant safety issues in designing the HTR-10 reactor

    International Nuclear Information System (INIS)

    Sun Yuliang; Xu Yuanghui

    2001-01-01

    The HTR-10 is a 10 MWth pebble bed high temperature gas cooled reactor being constructed as a research facility at the Institute of Nuclear Energy Technology. This paper discusses design issues of the HTR-10 which are related to safety. It addresses the safety criteria used in the development and assessment of the design, the safety important systems, and the safety classification of components. It also summarises the results of safety analysis, including the approach used for the radioactive source term, as well as the approach to containment design. (author)

  14. SeaWiFS technical report series. Volume 26: Results of the SeaWiFS Data Analysis Round-Robin, July 1994 (DARR-1994)

    Science.gov (United States)

    Hooker, Stanford B. (Editor); Firestone, Elaine R. (Editor); Siegel, David A.; Obrien, Margaret C.; Sorensen, Jen C.; Konnoff, Daniel A.; Brody, Eric A.; Mueller, James L.; Davis, Curtiss O.; Rhea, W. Joseph

    1995-01-01

    The accurate determination of upper ocean apparent optical properties (AOP's) is essential for the vicarious calibration of the sea-viewing wide field-of-view sensor (SeaWiFS) instrument and the validation of the derived data products. To evaluate the role that data analysis methods have upon values of derived AOP's, the first Data Analysis Round-Robin (DARR-94) workshop was sponsored by the SeaWiFS Project during 21-23 July, 1994. The focus of this intercomparison study was the estimation of the downwelling irradiance spectrum just beneath the sea surface, E(sub d)(0(sup -), lambda); the upwelling nadir radiance just beneath the sea surface, L(sub u)(0(sup -), lambda); and the vertical profile of the diffuse attenuation coefficient spectrum, K(sub d)(z, lambda). In the results reported here, different methodologies from four research groups were applied to an identical set of 10 spectroradiometry casts in order to evaluate the degree to which data analysis methods influence AOP estimation, and whether any general improvements can be made. The overall results of DARR-94 are presented in Chapter 1 and the individual methods of the four groups are presented in Chapters 2-5. The DARR-94 results do not show a clear winner among data analysis methods evaluated. It is apparent, however, that some degree of outlier rejection is required in order to accurately estimate L(sub u)(0(sup -), lambda) or E(sub d)(0(sup -), lambda). Furthermore, the calculation, evaluation and exploitation of confidence intervals for the AOP determinations needs to be explored. That is, the SeaWiFS calibration and validation problem should be recast in statistical terms where the in situ AOP values are statistical estimates with known confidence intervals.

  15. MLR reactor

    International Nuclear Information System (INIS)

    Ryazantsev, E.P.; Egorenkov, P.M.; Nasonov, V.A.; Smimov, A.M.; Taliev, A.V.; Gromov, B.F.; Kousin, V.V.; Lantsov, M.N.; Radchenko, V.P.; Sharapov, V.N.

    1998-01-01

    The Material Testing Loop Reactor (MLR) development was commenced in 1991 with the aim of updating and widening Russia's experimental base to validate the selected directions of further progress of the nuclear power industry in Russia and to enhance its reliability and safety. The MLR reactor is the pool-type one. As coolant it applies light water and as side reflector beryllium. The direction of water circulation in the core is upward. The core comprises 30 FA arranged as hexagonal lattice with the 90-95 mm pitch. The central materials channel and six loop channels are sited in the core. The reflector includes up to 11 loop channels. The reactor power is 100 MW. The average power density of the core is 0.4 MW/I (maximal value 1.0 MW/l). The maximum neutron flux density is 7.10 14 n/cm 2 s in the core (E>0.1 MeV), and 5.10 14 n/cm 2 s in the reflector (E<0.625 eV). In 1995 due to the lack of funding the MLR designing was suspended. (author)

  16. Leaching of nuclear power reactor waste forms

    International Nuclear Information System (INIS)

    Endo, L.S.; Villalobos, J.P.; Miyamoto, H.

    1987-01-01

    The leaching tests for immobilized power reactor wastes carried out at IPEN are described. These wastes forms consist mainly of spent resins and boric acid concentrates solidified in ordinary Portland cement. All tests were conducted according to the ISO and IAEA recommendations. Three years leaching results are reported. The cesium diffuvity coefficients determined out of these results are about 1 x 10 -8 cm 2 /s for boric acid waste form and 9 x 10 -9 cm 2 /s for ion-exchange resin waste. Strontium diffusivity coefficients found are about 3 x 10 -11 cm 2 /s and 9 x 10 -11 cm 2 /s respectively. (Author) [pt

  17. 10 years Institute for Reactor Development

    International Nuclear Information System (INIS)

    1975-05-01

    Ten years ago the Institute of Reactor Development was founded. This report contains a review about the research work of the institute in these past ten years. The work was mainly performed within the framework of the Fast Breeder Project, the Nuclear Safety Project and Computer Aided Design. Especially the following topics are discussed: design studies for different fast breeder reactors, development works for fast breeders, investigations of central safety problems of sodium cooled breeder reactors (such as local and integral coolant disturbances and hypothetical accident analysis), special questions of light water reactor safety (such as dynamic stresses in pressure suppression systems and fuel rod behaviour under loss of coolant conditions), and finally computer application in various engineering fields. (orig.) [de

  18. The Core Flight System (cFS) Community: Providing Low Cost Solutions for Small Spacecraft

    Science.gov (United States)

    McComas, David; Wilmot, Jonathan; Cudmore, Alan

    2016-01-01

    In February 2015 the NASA Goddard Space Flight Center (GSFC) completed the open source release of the entire Core Flight Software (cFS) suite. After the open source release a multi-NASA center Configuration Control Board (CCB) was established that has managed multiple cFS product releases. The cFS was developed and is being maintained in compliance with the NASA Class B software development process requirements and the open source release includes all Class B artifacts. The cFS is currently running on three operational science spacecraft and is being used on multiple spacecraft and instrument development efforts. While the cFS itself is a viable flight software (FSW) solution, we have discovered that the cFS community is a continuous source of innovation and growth that provides products and tools that serve the entire FSW lifecycle and future mission needs. This paper summarizes the current state of the cFS community, the key FSW technologies being pursued, the development/verification tools and opportunities for the small satellite community to become engaged. The cFS is a proven high quality and cost-effective solution for small satellites with constrained budgets.

  19. Release of WIMS10: a versatile reactor physics code for thermal and fast systems - 15467

    International Nuclear Information System (INIS)

    Lindley, B.A.; Newton, T.D.; Hosking, J.G.; Smith, P.N.; Powney, D.J.; Tollit, B.; Smith, P.J.

    2015-01-01

    the WIMS code provides a versatile software package for neutronic calculations, which can be applied to all thermal reactor types including mixed moderator systems. It can provide lattice cell and supercell calculations using a range of flux solutions methods to produce the neutronic libraries for use in PANTHER or other whole core analysis codes. With the release of WIMS10, the range of problems which WIMS can solve has been greatly extended. A WIMS/PANTHER calculation route has been developed and validated for part MOX-fuelled PWRs, with calculations showing excellent agreement with 2D core deterministic and Monte Carlo transport solutions. A flexible geometry 3D method of characteristics transport solver, CACTUS3D has been added to the code. CACTUS3D has been benchmarked for a 3D BWR assembly model, and was in good agreement with a direct 172-group solution in the Monte Carlo code MONK. Fast reactor calculations using the ECCO deterministic calculation route have been validated using experimental data from the ZEBRA reactor. Power deposition can be treated through following neutrons and/or photons to their point of interaction. The improved methodology is shown to give more accurate calculation of heat deposition and improve agreement between calculated and measured detector responses for part MOX-fuelled cores. (authors)

  20. Modelling and optimisation of fs laser-produced K (alpha) sources

    Czech Academy of Sciences Publication Activity Database

    Gibbon, P.; Mašek, Martin; Teubner, U.; Lu, W.; Nicoul, M.; Shymanovich, U.; Tarasevitch, A.; Zhou, P.; Sokolowski-Tinten, K.; von der Linde, D.

    2009-01-01

    Roč. 96, č. 1 (2009), 23-31 ISSN 0947-8396 R&D Projects: GA MŠk(CZ) LC528 Institutional research plan: CEZ:AV0Z10100523 Keywords : fs laser-plasma interaction * K (alpha) sources * 3D numerical modelling Subject RIV: BL - Plasma and Gas Discharge Physics Impact factor: 1.595, year: 2009

  1. Research on intelligent monitor for 3D power distribution of reactor core

    International Nuclear Information System (INIS)

    Xia, Hong; Li, Bin; Liu, Jianxin

    2014-01-01

    Highlights: • Core power distribution of ex-core measurement system has been reconstructed. • Building up an artificial intelligence model for 3-D core power distribution. • Error of the experiments has been reduced to 0.76%. • Methods for improving the accuracy of the model have been obtained. - Abstract: A real-time monitor for 3D reactor power distribution is critical for nuclear safety and high efficiency of NPP’s operation as well as for optimizing the control system, especially when the nuclear power plant (NPP) works at a certain power level or it works in load following operation. This paper was based on analyzing the monitor for 3D reactor power distribution technologies used in modern NPPs. Furthermore, considering the latest research outcomes, the paper proposed a method based on using an ex-core neutron detector system and a neural network to set up a real time monitor system for reactor’s 3D power distribution supervision. The results of the experiments performed on a reactor simulation machine illustrated that the new monitor system worked very well for a certain burn-up range during the fuel cycle. In addition, this new model could reduce the errors associated with the fitting of the distribution effectively, and several optimization methods were also obtained to improve the accuracy of the simulation model

  2. Neutron flux calculations for the Rossendorf research reactor in (hex)- and (hex,z)-geometry using SNAP-3D

    International Nuclear Information System (INIS)

    Koch, R.; Findeisen, A.

    1986-04-01

    The multigroup neutron diffusion theory code SNAP-3D has been used to perform time independent neutron flux and power calculations of the 10 MW Rossendorf research reactor of the type WWR-SM. The report describes these calculations, as well as the actual reactor configuration, some details of the code SNAP-3D, and two- and three-dimensional reactor models. For evaluating the calculations some flux values and control rod worths have been compared with those of measurements. (author)

  3. Conceptual design of D-3He FRC reactor 'ARTEMIS'

    International Nuclear Information System (INIS)

    Momota, H.; Ishida, A.; Kohzaki, Y.

    1991-07-01

    A comprehensive design study of the D- 3 He fueled field-reversed configuration (FRC) reactor 'ARTEMIS' is carried out for the purpose of proving its attractive characteristics and clarifying the critical issues for a commercial fusion reactor. The FRC burning plasma is stabilized and sustained in a steady equilibrium by means of a preferential trapping of D- 3 He fusion-produced energetic protons. A novel direct energy converter for 15MeV protons is also presented. On the bases of a consistent scenario of the fusion plasma production and simple engineering, a compact and simple reactor concept is presented. The design of the D- 3 He FRC power plant definitely offers the most attractive prospect for energy development. It is environmentally acceptable in view of radio-activity and fuel resources; and the estimated cost of electricity is low compared to a light water reactor. Critical issues concerning physics or engineering for the development of the D- 3 He FRC reactor are clarified. (author)

  4. Beryllium and lithium resource requirements for solid blanket designs for fusion reactors

    International Nuclear Information System (INIS)

    Powell, J.R.

    1975-01-01

    The lithium and beryllium requirements are analyzed for an economy of 10 6 MW(e) CTR 3 capacity using solid blanket fusion reactors. The total lithium inventory in fusion reactors is only approximately 0.2 percent of projected U. S. resources. The lithium inventory in the fusion reactors is almost entirely 6 Li, which must be extracted from natural lithium. Approximately 5 percent of natural lithium can be extracted as 6 Li. Thus the total feed of natural lithium required is approximately 20 times that actually used in fusion reactors, or approximately 4 percent of U. S. resources. Almost all of this feed is returned to the U. S. resource base after 6 Li is extracted, however. The beryllium requirements are on the order of 10 percent of projected U. S. resources. Further, the present cost of lithium and the cost of beryllium extraction could both be increased tenfold with only minor effects on CTR capital cost. Such an increase should substantially multiply the economically recoverable resources of lithium and beryllium. It is concluded that there are no lithium or beryllium resource limitations preventing large-scale implementation of solid blanket fusion reactors. (U.S.)

  5. Small Incision Lenticule Extraction (SMILE) versus Femtosecond Laser-Assisted In Situ Keratomileusis (FS-LASIK) for Myopia: A Systematic Review and Meta-Analysis

    Science.gov (United States)

    Shen, Zeren; Shi, Keda; Yu, Yinhui; Yu, Xiaoning; Lin, Yuchen; Yao, Ke

    2016-01-01

    Purpose The goal of this study was to compare small incision lenticule extraction (SMILE) with femtosecond laser-assisted in situ keratomileusis (FS-LASIK) for treating myopia. Methods The CENTRAL, EMBASE, PubMed databases and a Chinese database (SinoMed) were searched in May of 2016. Twelve studies with 1,076 eyes, which included three randomized controlled trials (RCTs) and nine cohorts, met our inclusion criteria. The overall quality of evidence was evaluated using the Grading of Recommendations Assessment, Development and Evaluation (GRADE) working group framework. Data were extracted and analysed at three to six months postoperatively. Primary outcome measures included a loss of one or more lines of best spectacle corrected visual acuity (BSCVA), uncorrected visual acuity (UCVA) of 20/20 or better, mean logMAR UCVA, postoperative mean spherical equivalent (SE) and postoperative refraction within ±1.0 D of the target refraction. Secondary outcome measures included ocular surface disease index (OSDI), tear breakup time (TBUT) and Schirmer’s 1 test (S1T) as dry eye parameters, along with corneal sensitivity. Results The overall quality of evidence was considered to be low to very low. Pooled results revealed no significant differences between the two groups with regard to a loss of one or more lines in the BSCVA (OR 1.71; 95% CI: 0.81, 3.63; P = 0.16), UCVA of 20/20 or better (OR 0.71; 95% CI: 0.44, 1.15; P = 0.16), logMAR UCVA (MD 0.00; 95% CI: -0.03, 0.04; P = 0.87), postoperative refractive SE (MD -0.00; 95% CI: -0.05, 0.05; P = 0.97) or postoperative refraction within ±1.0 D of the target refraction (OR 0.78; 95% CI: 0.22, 2.77; P = 0.70) within six months postoperatively. The pooled analysis also indicated that the FS-LASIK group suffered more severely from dry eye symptoms (OSDI; MD -6.68; 95% CI: -11.76, -2.00; P = 0.006) and lower corneal sensitivity (MD 12.40; 95% CI: 10.23, 14.56; P LASIK and SMILE are safe, effective and predictable surgical

  6. Management of the radioactive waste resulting from the Romanian VVR-S research reactor decommissioning

    International Nuclear Information System (INIS)

    Ene, D.; Cepraga, D.G.

    2002-01-01

    The paper consists in a waste study of the Romanian VVR-S reactor which will be prepared for decommissioning operations after the permanent shutdown (23.12.1997). Calculations were carried out to determine the activity arising from neutron activation of structural materials inside the reactor, considering the design of the facility and its operating rules. To this end, the following method was used: i) Neutron flux distribution within the reactor was calculated using the DORT transport code, based on DLC23 shielding library relating to three cylindrical reference systems of the reactor structure: reactor core, horizontal tube and thermal column; ii) Calculation of the activity of each reactor component at different cooling times was performed by the ANITA2000 code, using the neutron flux, compositional data for each material and the power history of the reactor; iii) Unconditional clearance indexes for all material at various cooling times were calculated using the clearance levels defined in IAEA-TECDOC-855; iv) Total activities and masses by material type, within the waste category and for each decay time were calculated by summation of the data previously classified for each reactor component. The resulting activation inventory and waste masses, falling in IAEA defined waste categories are presented in the paper at periods of 100 days, and 6, 10, 25, and 50 years after reactor the shutdown. For some components of the reactor as: aluminum central vessel, the central iron shielding ring, the time behaviour of both the fin spatial activity distribution and the radionuclide contributions to the total activity are plotted in the paper. (author)

  7. Small Incision Lenticule Extraction (SMILE) vs. Femtosecond Laser in Situ Keratomileusis (FS-LASIK) for treatment of myopia

    DEFF Research Database (Denmark)

    Hansen, Rasmus Søgaard; Lyhne, Niels; Justesen, Birgitte

    Purpose: - 67 ord LASIK has been the dominating corneal refractive procedure for almost two decades, but the new flap-free SMILE procedure has shown promising results. The aim of this study was to evaluate and compare refractive predictability, uncorrected and corrected distance visual acuity (UDVA...... and CDVA), and safety at 1 day, 1 week and 3 months after SMILE and FS-LASIK for all degrees of myopia, but in particular high myopia. Setting: Department of Ophthalmology, Odense University Hospital, Odense, Denmark Methods: - 157 ord Retrospective study of results after SMILE and FS-LASIK for all degrees...... having undergone re-treatment. The SMILE treatments and FS-LASIK flaps were performed with a VisuMax® femtosecond laser (Carl Zeiss-Meditec, Jena, Germany). The FS-LASIK photoablation was performed with a MEL-80 flying-spot excimer laser with eye-tracker (Carl Zeiss-Meditec, Jena, Germany). In SMILE...

  8. LTS and FS inhibitory interneurons, short-term synaptic plasticity, and cortical circuit dynamics.

    Directory of Open Access Journals (Sweden)

    Itai Hayut

    2011-10-01

    Full Text Available Somatostatin-expressing, low threshold-spiking (LTS cells and fast-spiking (FS cells are two common subtypes of inhibitory neocortical interneuron. Excitatory synapses from regular-spiking (RS pyramidal neurons to LTS cells strongly facilitate when activated repetitively, whereas RS-to-FS synapses depress. This suggests that LTS neurons may be especially relevant at high rate regimes and protect cortical circuits against over-excitation and seizures. However, the inhibitory synapses from LTS cells usually depress, which may reduce their effectiveness at high rates. We ask: by which mechanisms and at what firing rates do LTS neurons control the activity of cortical circuits responding to thalamic input, and how is control by LTS neurons different from that of FS neurons? We study rate models of circuits that include RS cells and LTS and FS inhibitory cells with short-term synaptic plasticity. LTS neurons shift the RS firing-rate vs. current curve to the right at high rates and reduce its slope at low rates; the LTS effect is delayed and prolonged. FS neurons always shift the curve to the right and affect RS firing transiently. In an RS-LTS-FS network, FS neurons reach a quiescent state if they receive weak input, LTS neurons are quiescent if RS neurons receive weak input, and both FS and RS populations are active if they both receive large inputs. In general, FS neurons tend to follow the spiking of RS neurons much more closely than LTS neurons. A novel type of facilitation-induced slow oscillations is observed above the LTS firing threshold with a frequency determined by the time scale of recovery from facilitation. To conclude, contrary to earlier proposals, LTS neurons affect the transient and steady state responses of cortical circuits over a range of firing rates, not only during the high rate regime; LTS neurons protect against over-activation about as well as FS neurons.

  9. Theory of superconducting spintronic SIsFS devices

    International Nuclear Information System (INIS)

    Bakurskiy, S.V.; Klenov, N.V.; Soloviev, I.I.; Kupriyanov, M.Yu.; Bol'ginov, V.V.; Ryazanov, V.V.; Vernik, I.V.; Mukhanov, O.A.; Golubov, A.A.

    2013-01-01

    Full text: Motivated by recent progress in developments of cryogenic memory compatible with single flux quantum (SFQ) circuits we have performed a theoretical study of magnetic SIsFS Josephson junctions, where 'S' is a bulk superconductor, 's' is a thin superconducting film, 'F' is a metallic ferromagnet and 'I' is an insulator. We calculate the Josephson current as a function of s and F layers thickness, temperature and exchange energy of F film. We outline several modes of operation of these junctions and demonstrate their unique ability to have high I C R N product in the π-state, comparable to that in SIS tunnel junctions commonly used in SFQ circuits. We develop a model describing switching of the Josephson critical current in these devices by external magnetic field. The results are in good agreement with the experimental data for Nb-Al/AlOx-Nb-Pd0:99Fe0:01-Nb junctions. This work is supported by RFBR No. 12-02-90010-Bel a .

  10. Determination of the working voltage of the RP-0 and RP-10 nuclear reactors starting chains

    International Nuclear Information System (INIS)

    Zuniga, Agustin; Veramendi, Emilio; Salazar, Alberto

    2014-01-01

    This report presents the determination of the voltage curve of the RP-0 and RP-10 nuclear reactor starting chains, as an approach for determining the working voltages. The method consisted in changing the voltage and recording the corresponding counts. Then, the area of the best response was determined according to the detector characteristics, and also was found that for the RP-0, the response was in the proportional region, meanwhile for the RP-10, the response was in the region of ionization chambers. The values obtained were: BF3-A3 (RP-0) and 1150 V for RP-10, CF-A1 = 400 V, CF-A2 = 400 V, CF-A3 = 400 V. (authors).

  11. U.S. activities related to fast reactors and ADS

    International Nuclear Information System (INIS)

    Finck, Phillip J.

    2001-01-01

    The U.S. nuclear power industry achieved its second straight year of record power generation levels during 2000. Total power generated was 753.9 billion kWh, 3.5 percent above the previous record of 728.1 billion kWh set in 1999. Recent years of reliable service and declining production costs have led to increased industry interest in nuclear power plant license renewal. The Nuclear Regulatory Commission approved the license renewal applications for five U.S. nuclear power plants in 2000. Five additional applications were received and 28 more are planned to be submitted by 2004. Concerns over energy resource availability, climate change, air quality, and energy security suggest an important role for nuclear power in future energy supplies. While the current Generation II and III nuclear power plant designs provide an economically, technically, and publicly acceptable electricity supply in many markets, further advances in nuclear energy system design can broaden the opportunities for the use of nuclear energy. To explore these opportunities, the U. S. Department of Energy's Office of Nuclear Energy, Science and Technology has engaged governments, industry, and the research community worldwide in a wide-ranging discussion on the development of next-generation nuclear energy systems known as 'Generation IV'. The I-NERI program has the following objectives: Develop advanced concepts and scientific breakthroughs in nuclear fission and reactor technology to address and overcome the principal technical and scientific obstacles to the expanded use of nuclear energy worldwide; Promote bilateral and multilateral collaboration with international agencies and research organizations to improve development of nuclear energy; and Promote and maintain nuclear science and engineering infrastructure to meet future technical challenges. I-NERI will sponsor innovative research and development in the following areas: Next-generation nuclear energy plant designs with higher efficiency

  12. Removal in a lump of JRR-3 nuclear reactor

    International Nuclear Information System (INIS)

    Ohnishi, Nobuaki; Suzuki, Masanori; Nagase, Tetsuo; Watanabe, Morinari.

    1989-01-01

    The research reactor JRR-3 in Japan Atomic Energy Research Institute is called 'Home made No.1 reactor' as all except fuel and heavy water as the moderator and coolant were manufactured in Japan. The JRR-3 attained the criticality in 1962, and the cumulative time of operation reached 47135.5 hours, and the cumulative power output reached 419073.5 MWh. It was stopped in 1983. During the period, it was utilized for beam experiment, irradiation of fuel and materials, RI production and others. In order to cope with the expansion of utilization and the advance of utilizing technology of the research reactor, the reconstruction works are in progress, and the criticality of the reconstructed reactor is expected in 1990. On the site where the old reactor is removed, the reactor of different type is installed, and the first large cold neutron source is equipped. In this report, as to the removal of the old reactor proper, the method of working and the results are described. Considering the period of working, the cost and the management of the removed reactor, in the case of the JRR-3, the method of carrying it out in a lump was adopted as the optimum removal method. The plan, procedure and results of the removal working are reported. (K.I.)

  13. Optical Waveform Sampling and Error-Free Demultiplexing of 1.28 Tb/s Serial Data in a Nanoengineered Silicon Waveguide

    DEFF Research Database (Denmark)

    Ji, Hua; Pu, Minhao; Hu, Hao

    2011-01-01

    This paper presents the experimental demonstrations of using a pure nanoengineered silicon waveguide for 1.28 Tb/s serial data optical waveform sampling and 1.28 Tb/s–10 Gb/s error free demultiplexing. The 330-fs pulses are resolved in each 780-fs time slot in waveform sampling. Error...

  14. 3 MW TRIGA Research Reactor facility of BAEC and its Utilization

    Energy Technology Data Exchange (ETDEWEB)

    Molla, N.I.; Bhuiyan, S.I.; Wadud Mondal, M.A.; Ahmed, F.U.; Islam, M.N.; Hossain, S.M.; Ahmed, K.; Zulquarnain, A.; Abedin, Z. [Bangladesh Atomic Energy Commission, Atomic Energy Research Establishment, Dhaka (Bangladesh)

    1999-08-01

    The paper briefly describes the Utilisation of 3 MW TRIGA Research Reactor of BAEC for neutron beam research, neutron activation analysis are isotope production. It includes the installation of the triple axis neutron spectrometer at the radial piercing beam port and a neutron radiography set-up at the tangential beam port and their uses for material analysis and condensed matter research and material testing. Nuclear and magnetic structures of some ferrites have been studied in powder diffraction method in the double axis mode. SANS technique with double crystal diffraction known as Bonse and Hart's method has been adopted in an experiment with alumina sample. The neutron radiography set-up and its use in the detection of corrosion in alumina have been reported. Determination of arsenic concentration in drinking water from tube well via Instrumental Neutron Activation Analysis and production of radioiodine-131 by dry distillation method are presented. Our experience on the removal of N-16 decay tank because of the leakage of coolant and bringing the research reactor back to operational by-passing the decay tank have been focussed. A possible reconfiguration of the existing TRIGA core, without exceeding the safety margins, providing additional irradiation channel and upgrading the neutron flux for increased radioisotope production has been attempted. Cross section library ENDF/B-VI and JENDL3.2, code NJOY94.10, WIMSD package, 3-D code CITATION, PARET and Monte Carlo code MCNP4B2 have been employed to achieve the objective. (author)

  15. 3D simulation of CANDU reactor regulating system

    International Nuclear Information System (INIS)

    Venescu, B.; Zevedei, D.; Jurian, M.

    2013-01-01

    Present paper shows the evaluation of the performance of the 3-D modal synthesis based reactor kinetic model in a closed-loop environment in a MATLAB/SIMULINK based Reactor Regulating System (RRS) simulation platform. A notable advantage of the 3-D model is the level of details that it can reveal as compared to the coupled point kinetic model. Using the developed RRS simulation platform, the reactor internal behaviours can be revealed during load-following tests. The test results are also benchmarked against measurements from an existing (CANDU) power plant. It can be concluded that the 3-D reactor model produces more realistic view of the core neutron flux distribution, which is closer to the real plant measurements than that from a coupled point kinetic model. It is also shown that, through a vectorization process, the computational load of the 3-D model is comparable with that of the 14-zone coupled point kinetic model. Furthermore, the developed Graphical User Interface (GUI) software package for RRS implementation represents a user friendly and independent application environment for education training and industrial utilizations. (authors)

  16. Manila on CephFS at CERN

    CERN Document Server

    Wiebalck, Arne

    2017-01-01

    In response to the user demand for a light-weight provisioning of distributed file system shares, the OpenStack and Ceph teams at CERN have recently added Manila/CephFS to their service catalogues. While leveraging the operational experience with a 190'000 core OpenStack deployment and a 12 PB Ceph cluster for such a self-service kiosque suggested itself, the service design and setup phases were followed by a number of functionality and stress tests to ensure the individual components are ready for production use. The final service design and the results obtained during the pre-production phase, for instance when scaling to a large number of Manila and CephFS clients or the integration with Magnum/Kubernetes, will be presented alongside the initial use cases and our first experiences running these new services in production.

  17. Extension of the reactor dynamics code MGT-3D for pebblebed and blocktype high-temperature-reactors

    International Nuclear Information System (INIS)

    Shi, Dunfu

    2015-01-01

    The High Temperature Gas cooled Reactor (HTGR) is an improved, gas cooled nuclear reactor. It was chosen as one of the candidates of generation IV nuclear plants [1]. The reactor can be shut down automatically because of the negative reactivity feedback due to the temperature's increasing in designed accidents. It is graphite moderated and Helium cooled. The residual heat can be transferred out of the reactor core by inactive ways as conduction, convection, and thermal radiation during the accident. In such a way, a fuel temperature does not go beyond a limit at which major fission product release begins. In this thesis, the coupled neutronics and fluid mechanics code MGT-3D used for the steady state and time-dependent simulation of HTGRs, is enhanced and validated [2]. The fluid mechanics part is validated by SANA experiments in steady state cases as well as transient cases. The fuel temperature calculation is optimized by solving the heat conduction equation of the coated particles. It is applied in the steady state and transient simulation of PBMR, and the results are compared to the simulation with the old overheating model. New approaches to calculate the temperature profile of the fuel element of block-type HTGRs, and the calculation of the homogeneous conductivity of composite materials are introduced. With these new developments, MGT-3D is able to simulate block-type HTGRs as well. This extended MGT-3D is used to simulate a cuboid ceramic block heating experiment in the NACOK-II facility. The extended MGT-3D is also applied to LOFC and DLOFC simulation of GT-MHR. It is a fluid mechanics calculation with a given heat source. This calculation result of MGT-3D is verified with the calculation results of other codes. The design of the Japanese HTTR is introduced. The deterministic simulation of the LOFC experiment of HTTR is conducted with the Monte-Carlo code Serpent and MGT-3D, which is the LOFC Project organized by OECD/NEA [3]. With Serpent the burnup

  18. An Account of Oak Ridge National Laboratory's Thirteen Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Rosenthal, Murray Wilford [ORNL

    2009-08-01

    The Oak Ridge National Laboratory has built and operated 13 nuclear reactors in its 66-year history. The first was the graphite reactor, the world's first operational nuclear reactor, which served as a plutonium production pilot plant during World War II. It was followed by two aqueous-homogeneous reactors and two red-hot molten-salt reactors that were parts of power-reactor development programs and by eight others designed for research and radioisotope production. One of the eight was an all-metal fast burst reactor used for health physics studies. All of the others were light-water cooled and moderated, including the famous swimming-pool reactor that was copied dozens of times around the world. Two of the reactors were hoisted 200 feet into the air to study the shielding needs of proposed nuclear-powered aircraft. The final reactor, and the only one still operating today, is the High Flux Isotope Reactor (HFIR) that was built particularly for the production of californium and other heavy elements. With the world's highest flux and recent upgrades that include the addition of a cold neutron source, the 44-year-old HFIR continues to be a valuable tool for research and isotope production, attracting some 500 scientific visitors and guests to Oak Ridge each year. This report describes all of the reactors and their histories.

  19. Radiobiological aspects of application of BR-10 reactor neutrons for radiotherapy of malignant tumours

    International Nuclear Information System (INIS)

    Ul'yanenko, S.E.; Kuznetsova, M.N.; Obaturov, G.M.

    1992-01-01

    Possibilities to increase the factor of therapeutical gain (FTG) by optimizing irradiation conditions and using hyperglycemia were studied. It is shown that relative biological effectiveness (RBE) of neutrons in fission spectrum of the BR-10 reactor in the dose range from 10 Gy used one time is 4.2-4.5 for tumours and 4.0-4.2 for normal skin; in case of fractionated irradiation by neutrons (1-8 fractions in the range of 6-10 Gy) RBE increases practically 1.5 fold; employment of neutron beam filters and hyperglycemia in conditions of combined gamma-neutron procedures of irradiation permits a considerable increase in FTG. 3 refs

  20. Analyses for MARIA Research Reactor with RELAP/MOD3 code

    International Nuclear Information System (INIS)

    Szczurek, J.; Czerski, P.

    2004-01-01

    This paper deals with the application of the RELAP5/MOD3 code to the transient analyses for MARIA research reactor. Poland's MARIA Research Reactor is water and beryllium moderated, water-cooled reactor of a pool type with pressurized fuel channels containing concentric multi-tube assemblies of highly enriched uranium clad in aluminium. The RELAP5/MOD3 input data model includes the whole primary cooling circuit of the MARIA reactor. The model was qualified against the reactor data at steady state conditions and additionally against the existing reliable experimental data for a transient initiated by the reactor scram. The RELAP transient simulation was performed for loss of forced flow accidents including two scenarios with protected and unprotected (no scram) reactor core. Calculations allow estimating time margin for reactor scram initiation and reactivity feedbacks contribution to the results. (author)

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